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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:NRC TO UTILITY
MONTHYEARML20062G5471990-11-26026 November 1990 Forwards Summary of NRC Understanding of Current Status of Unimplemented GSIs at Facility ML20058H5501990-11-14014 November 1990 Forwards Insp Repts 50-445/90-40 & 50-446/90-40 on 900918- 1030.Violations Noted But Not Cited IR 05000445/19900371990-11-0808 November 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-445/90-37 & 50-446/90-37 ML20058G1521990-11-0505 November 1990 Discusses Util 900529 Response to 900402 Notice of Violation.Violations 445/8923-V-01 & 446/8923-V-01 Closed, Per Insp Repts 50-445/89-23 & 50-446/89-23 ML20058G4791990-10-31031 October 1990 Forwards Summary of 901022 Meeting W/Util in Arlington,Tx Re Secondary Plant Reliability Problems at Unit 1 ML20058E6931990-10-29029 October 1990 Forwards Generic Fundamentals Exam Section of Written Operator Licensing Exam Administered on 901010 ML20058D0261990-10-26026 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-445/90-36 & 50-446/90-36 ML20058A7121990-10-19019 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-445/90-16 & 50-446/90-16 on 900806 ML20058A0971990-10-10010 October 1990 Forwards Insp Repts 50-445/90-31 & 50-446/90-31 on 900807- 0918 & Notice of Violation ML20062B2211990-10-0909 October 1990 Requests Response to Question Re Facility Cold Overpressure Mitigation Sys Actuation During Accident Events.Response Requested by 901214 ML20059N4711990-10-0303 October 1990 Ack Receipt of Forwarding Rev 8 to Physical Security Plan.Changes Consistent w/10CFR50.54(p) ML20059K3361990-09-17017 September 1990 Forwards Insp Repts 50-445/90-36 & 50-446/90-36 on 900820- 24 & Notice of Violation ML20059J9861990-09-13013 September 1990 Forwards Info Re Generic Fundamentals Exam Section of Operator Licensing Exam to Be Administered on 901010.Results of Exam Should Be Available within 3 Wks of Completion ML20059K3581990-09-13013 September 1990 Ack Receipt of 900820 Revised Response to Violations Noted in Insp Repts 50-445/89-57 & 50-446/89-57 ML20059K3561990-09-13013 September 1990 Ack Receipt of 900904 Response to Violations Noted in Insp Repts 50-445/90-22 & 50-446/90-22 ML20059J6171990-09-11011 September 1990 Forwards Insp Repts 50-445/90-30 & 50-446/90-30 on 900723- 0802.No Violations or Deviations Noted ML20059J2451990-09-10010 September 1990 Forwards Insp Repts 50-445/90-29 & 50-446/90-29 on 900723-27.No Violations Noted ML20059E2301990-08-31031 August 1990 Forwards Insp Repts 50-445/90-26 & 50-446/90-26 on 900705-0807.No Violations or Deviations Noted ML20059F3021990-08-30030 August 1990 Forwards Insp Repts 50-445/90-28 & 50-446/90-28 on 900716-20.No Violations or Deviations Noted ML20059D6511990-08-29029 August 1990 Forwards Insp Repts 50-445/90-34 & 50-446/90-34 on 900731- 0807 & Notice of Violation.Action Already Taken to Correct Hot Standby Operating Procedure Inadequacies & No Response to Violation Required ML20059D7791990-08-28028 August 1990 Forwards Investigation Synopsis Re Alleged Attempt to Inhibit Employee from Bringing Safety Concerns to Nrc. Investigation Completed in Apr 1990 ML20056B2681990-08-22022 August 1990 Advises That 881130,890313,0526 & 0920 Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss Acceptable ML20059A5891990-08-15015 August 1990 Ack Receipt of 900730 Response to Violations Noted in Insp Repts 50-445/90-19 & 50-446/90-19 ML20058M2271990-08-0606 August 1990 Forwards Insp Repts 50-445/90-16 & 50-446/90-16 on 900423-27.Unresolved Item Identified.Inspector Determined That Key Emergency Response Personnel Not Always Proficient in Some Duties ML20058M2441990-08-0303 August 1990 Forwards Insp Repts 50-445/90-22 & 50-446/90-22 on 900606-0703 & Notice of Violation.Written Response Requested Based on Specifics Contained in Notice ML20056A1741990-07-30030 July 1990 Advises That Written & Operating Licensing Exams Scheduled for Wk of 901126.Licensee Should Furnish Ref Matl Listed in Encl 1 by 900904 ML20056A1161990-07-27027 July 1990 Forwards Summary of 900717 Meeting in Region IV Ofc Re Const Restart for Unit 2.List of Attendees & Viewgraphs Also Encl ML20055J1481990-07-27027 July 1990 Forwards Performance Assessment Repts 50-445/90-20 & 50-446/90-02 on 900529-0615.Startup Test Program Conducted in Safe & Prof Manner & Facility Operation Could Proceed Above 50% Power ML20055J4311990-07-26026 July 1990 Advises That 900601 Rev 7 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable. Portions of Plan Administrative in Nature & Do Not Reduce Plan Effectiveness ML20056A0441990-07-25025 July 1990 Grants Temporary Waiver of Compliance from Tech Specs 3.3.2 & 3.6.2.1 Re Containment Spray Sys in Order to Repair & Test Containment Pressure Transmitter 1-PT-0934 W/Unit in Hot Standby ML20055G7671990-07-20020 July 1990 Ack Receipt of in Response to 900705 Telcon Re Acceptability of THERMO-LAG Fire Barrier Matl.Correspondence Reviewed & Matter Closed ML20055G8701990-07-20020 July 1990 Forwards Insp Repts 50-445/90-23 & 50-446/90-23 on 900618-22.No Violations or Deviations Noted ML20055G0541990-07-13013 July 1990 Forwards Insp Repts 50-445/90-24 & 50-446/90-24 on 900618-22 & 25-28.No Violations or Deviations Identified ML20056A0051990-07-11011 July 1990 Advises That NRC Draft Document Re Concerns Associated W/ Util 891229 Response to Insp Repts 50-445/89-60 & 50-446/89-60 Being Placed in Pdr.Opinions in Draft Do Not Constitute Final Agency Position ML20055E8231990-07-0909 July 1990 Advises of Maint Team Insp Scheduled for Wks of 901015,29 & 1105 at Plant & Confirms Telcon Between to Mckernon & T Hope Re Insp.Team Plans to Hold Meeting W/Util at Plant Site on 901002-04 to Define Scope of Insp.List of Matls Needed Encl ML20055E4871990-07-0303 July 1990 Expresses Appreciation for Volunteering to Participate in Emergency Response Data Sys (Erds).Implementation of ERDS Will Prove to Be Beneficial to Both NRC & Util.Survey Designed to Provide Hardware & Communications Info Encl ML20055D4201990-06-29029 June 1990 Forwards Insp Repts 50-445/90-19 & 50-446/90-19 on 900503-0605 & Notice of Violation.Util Should Review Strike Contingency Plans or Procedures to Assure That Appropriate Plans in Place Before Next Strike Negotiation Deadline ML20055C7611990-06-15015 June 1990 Concludes That Plant Equipment,Program & Personnel Performance Adequate & That Testing Program Can Continue Above 50% Power Plateau to full-power,per Insp Repts 50-445/90-20 & 50-446/90-20 to Be Issued at Later Date ML20059M8611990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248H1751989-10-0303 October 1989 Discusses Submittal of Proprietary & Copyrighted Matl W/O Proper Indication.Guidelines & Procedures to Be Followed Re Proprietary & Copyrighted Matl Provided ML20248D2341989-09-29029 September 1989 Forwards Emergency Response Guidelines (Ergs) Insp Repts 50-445/89-59 & 50-446/89-59 on 890814-25.Weaknesses & Unresolved Item Noted.Engineering Task Group Developed to Resolve Number of Engineering Items Re ERGs ML20248A6481989-09-26026 September 1989 Forwards Insp Repts 50-445/89-64 & 50-446/89-64 on 890802- 0905 & Notices of Violation & Deviation ML20248A5031989-09-26026 September 1989 Forwards Insp Repts 50-445/89-66 & 50-446/89-66 on 890802- 0905 & Notice of Violation ML20247R5801989-09-26026 September 1989 Forwards Insp Repts 50-445/89-63 & 50-446/89-63 on 890802-0905.No Violations or Deviations Noted ML20248E2671989-09-22022 September 1989 Advises That 880517 Response to Generic Ltr 88-03, Steam Binding of Auxiliary Feedwater Pumps Satisfactory ML20248B9591989-09-22022 September 1989 Forwards Insp Repts 50-445/89-65 & 50-446/89-65 on 890802- 0905 & Notice of Violation 1990-09-17
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M5711999-10-20020 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 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 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 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 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 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 ML20211C4571999-08-16016 August 1999 Forwards Omitted Subj Page of Contractor TER 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 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 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 ML20210K2321999-07-29029 July 1999 Forwards Insp Repts 50-445/99-12 & 50-446/99-12 on 990530-0710.No Violations Noted 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 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 ML20209H7501999-07-15015 July 1999 Forwards Safety Evaluation on GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Comanche Peak Steam Electric Station,Units 1 & 2 ML20209G7421999-07-0808 July 1999 Forwards SER Concluding That Licensee Individual Plant Exam of External Events Process Capable of Identifying Most Likely Severe Accidents & Severe Accident Vulnerabilities & IPEEE Met Intent of Supp 4 to GL 88-20 ML20196L0121999-07-0808 July 1999 Forwards Safety Evaluation Granting First 10-Year Interval Inservice Insp Requests for Relief B-6 (Rev 2),B-7 (Rev 2), B-12,B-13,B-14 & C-9,pursuant to Tile 10CFR50.55a(g)(6)(i) ML20196K6771999-07-0202 July 1999 Ack Receipt of & Encl Scenario for Comanche Peak Steam Electric Station Emergency Plan Exercise Scheduled for 990721-22.Determined That Exercise Scenario Sufficient to Meet Emergency Plan Requirements & Exercise Objectives ML20196J4881999-06-29029 June 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1,NRC Revised Info in Rvid & Releasing Rvid as Version 2 ML20196J0401999-06-29029 June 1999 Forwards Safety Evaluation Re Plant,Units 1 & 2 Proposed Changes to Emergency Plan ML20196E6641999-06-22022 June 1999 Forwards Insp Repts 50-445/99-11 & 50-446/99-11 on 990418- 0529.No Violations Noted.Licensee Conduct of Activities Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance & Acceptable Radiological Control ML20207H3801999-06-0909 June 1999 Forwards Insp Repts 50-445/99-08 & 50-446/99-08 on 990503-11.Violations Identified & Being Treated as Noncited Violations ML20195G3771999-06-0909 June 1999 Ack Receipt of Ltr & Encl Objectives for Comanche Peak Steam Electric Station Emergency Plan Exercise Scheduled for 990721.Based on Review,Nrc Determined That Exercise Objectives,Appropriate to Meet Plan Requirements ML20207G3291999-06-0707 June 1999 Ack Receipt of Which Transmitted Rev 27 to Comanche Peak Steam Electric Station EP Under Provisions of 10CFR50.54(q).Based on Determination That Changes Do Not Decrease Effectiveness of EP No NRC Approval Required ML20207E9291999-06-0202 June 1999 Discusses 990526 Request That USNRC Exercise Discretion Not to Enforce Compliance with TS 4.8.2.1e Re Performance of Battery Performance Discharge Test,In Lieu of Battery Svc Test.Concludes Action Satisfactory & Discretion Exercised ML20207D7111999-05-28028 May 1999 Advises That Info Contained in Licensee 990514 Submittal Re License Amend Request 98-01-0 Will Be Withheld from Public Disclosure,Per 10CFR2.790. 10CFR2.790 ML20207D7011999-05-27027 May 1999 Advises That Info Contained in TU Electric 990514 Submittal (TXX-99115) Re License Amend Request 98-010 Will Be Withheld from Public Disclosure (Ref 10CFR2.790),per 990511 Application & Affidavit ML20207B7241999-05-25025 May 1999 Advises That Info Contained in Application & Affidavit 990507 (CAW-99-1333),submitting WCAP-15004,dtd Dec 1997,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20206Q0031999-05-14014 May 1999 Forwards Safety Evaluation Accepting Licensee Response to GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Comanche Peak Steam Electric Station,Unit 1 ML20206P5961999-05-12012 May 1999 Forwards Insp Repts 50-445/99-09 & 50-446/99-09 on 990419- 23.No Violations Noted.Nrc Determined That Releases of Radioactive Waste Effluents Controlled,Monitored & Quantified Well ML20206N7061999-05-12012 May 1999 Informs That NRC Ofc of NRR Reorganized,Effective 990328. Reorganization Chart Encl ML20206S5841999-05-11011 May 1999 Forwards Insp Repts 50-445/99-07 & 50-446/99-07 on 990307-0417.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint & Acceptable Radiological Controls ML20206K0311999-05-0707 May 1999 Informs That on 990407,NRC Administered Gfes of Written Operator Licensing Exam.Licensee Facility Did Not Participate in Exam,However,Copy of Master Exam with Answer Key Encl for Info,Without Encl ML20206H1701999-05-0606 May 1999 Forwards Copy of Exemption & Safety Evaluation Supporting Requirement in App K to 10CFR50.Proposal Will Use New Feedwater Flow Measurement Sys to Allow More Accurate Measurement to Thermal Power ML20206K3931999-05-0505 May 1999 Ltr Contract,Task Order 41, Comanche Peak Safety System Engineering Insp, Under Contract NRC-03-98-021 ML20206G1221999-05-0303 May 1999 Discusses 981215 Request That Document, Responses & Further Clarifications to NRC Questions from 980929 Meeting, Be Withheld from Public Disclosure.Determined Information to Be Proprietary & Will Be Withheld from Public Disclosure ML20206F5711999-04-30030 April 1999 Forwards Insp Repts 50-445/99-06 & 50-446/99-06 on 990329-0402.No Violations Noted.Insp Re Focus on Radiation Protection Program Activities During Unit 2 Refueling Outage ML20206E5211999-04-27027 April 1999 Discusses GL 96-01 Issued on 960110 & TU Responses, ,970102 & 980502 for Cpses,Units 1 & 2.Determined That Submittals Provided Both Info Requested & Responses Required by GL 96-01 ML20206B3831999-04-23023 April 1999 Forwards FEMA Final Rept for 990311,Comanche Peak Steam Electric Station Medical Drill.No Deficiencies or Areas Requiring Corrective Actions Identified ML20206B5321999-04-22022 April 1999 Ack Receipt of Ltrs Dtd 970407,09 & 0204,which Transmitted Revs 6 & 7 to Safeguards Continency Plan,Rev 10 to Security Training & Qualification Plan & Rev 29 to Physical Security Plan Submitted Under Provisions of 10CFR50.54(p) ML20206A2301999-04-14014 April 1999 Refers to Public Meeting Conducted on 990329 in Glen Rose, Tx Re Results of Plant Performance Review Completed on 990211 & Transmitted to Licensee on 990319.List of Attendees Encl ML20205L8711999-04-0707 April 1999 Forwards Insp Repts 50-445/99-03 & 50-446/99-03 on 990124-0306.No Violations Were Identified.Review of Operability Evaluation Re MOVs Disclosed That Licensee Failed to Include Info About Degraded ECCS Performance ML20205L1051999-04-0606 April 1999 Informs of Completion of Review of Tuec 980312 Submittal Re GL 97-05, SG Tube Insp Techniques. No Concerns Identified with SG Insp Techniques Employed at Cpses,Units 1 & 2,that Would Indicate Noncompliance with Current Licensing Basis ML20205F9141999-04-0101 April 1999 Informs That as of 990329 Dh Jaffe Has Been Assigned as Senior Project Manager for Plant IR 05000446/19920491999-03-24024 March 1999 Discusses Concern That Postulated Fire in CR Could Create Single Hot Short in Control Circuitry of MOVs Resulting in Spurious Operation.Required Hardware Mods Implemented to Control Circuits of Affected Mov,Per Insp Rept 50-446/92-49 ML20204F3311999-03-23023 March 1999 Forwards Discussion Items for 990323 Telcon 1999-09-07
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- 59 RE04 UNITED STATES o NUCLEAR REGULATORY COMMISSION
[ n REGION IV
- '. . .E 611 RYAN PLAZA DRIVE, SUITE 1000
'# AR Lf NGTON, TEXAS 76011
%*****/ October 26, 1978
In Reply Refer To: j RIV i Docket No. 50-445/Rpt. 78-17 50-446/Rpt. 78-17 l
l Texas Utilities Generating Company ATTN: Mr. R. J. Gary, Executive Vice President and General Manager 2001 Bryan Tower Dallas, Texas 75201 Gentlemen:
This refers to the investigation conducted by Messrs. J. J. Ward and R. G. Taylor of our staff on October 4-12, 1978, of activities authorized by NRC Construction Permit Nos. CPPR-126 and 127 for the Comanche Peak facility, Units No. 1 and 2, concerning the generic aspects of the failure of a Cadweld splice during fabrication operation The investigation and our findings are discussed in the enclosed investigation repor Within the scope of the investigation, no items of noncompliance were identifie In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the enclosed investigation report will be placed in the NRC's Public Document Roo If the report contains any information that you believe to be proprietary, it is necessary that you submit a written application to this office, within 20 days of the date of this letter requesting that such information be withheld from public disclosure. The application must include a full statement of the reasons why it is claimed that the information is proprietary. The application should be prepared so that any proprietary information identified is contained in an enclosure to the application, since the application without the enclosure will also be placed in the Public Document Room. If we do not hear from you in this regard within the specified period, the report will be placed in the Public Document Roo !
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Texas Utilities Generating Company -2- October 26, 1978 Should you have any questions concerning this investigation, we will be pleased to discuss them with yo
Sincerely,
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y I W. ' C. Seid14',) Chief ,
Reactor ConsYruction and-
' Engineering Support Branch
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Enclosure:
IE Investigation Report No. 50-445/78-17 50-446/78-17 .
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REGION IV==
Report No. 50-445/78-17; 50-446/78-17 Docket No. 50-445; 50-446 Category A2 Licensee: Texas Utilities Generating Company 2001 Bryan Tower Dallas, Texas 75201 Facility Name: Comanche Peak, Units 1 & 2 Investigation at: Comanche Peak Station and Off-Sita Investigation conducted: October 4-12, 1978 Inspector ? - /4/2.5'/7s R. G. Taylor, Resident Inspector, Projects Section Date
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/0f35'/7 y (/. J. Ward Investigation Specialist Date
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(Paragraph 4)
Approved: m /0/hf'/78 W. A. Crossman, Chief, Projects Section Date Inspection Summary:
Investigation on October 4-12, 1978 (Report No. 50-445/78-17;50-44S/78-17)
Areas Inspected: Special investigative inspection of generic aspects due to failure of a Cadweld splice during fabrication operations in Unit 1 Con-tainment Buildi.ng wall. The investigation involved sixteen inspector-hours by the CPSES Resident Inspector and the RIV Investigato Results: No generic aspects of the Cadweld splice failure were identifie AT[
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INTRODUCTION The Region IV Investigator and the IE Resident Inspector assigned to l Comanche Peak Steam Electric Station (CPSES) conducted an investigation !
related to generic aspects of poor workmanship in Cadweld splicing of the Unit 1 Containment wall reinforcing stee REASON FOR INVESTIGATION The licensee, on October 4, 1978, reported to the Resident Inspector an event that had occurred on October 2 and had the potential of being reportable under the requirements of 10 CFR 50.55(e). The licensee reported that a Cadweld splice in the Unit 1 Containment wall reinforc-ing steel had pulled apart upon application of a light force while pre- ;
paring the spliced bar for additional splicing. The mode of failure I was such that grossly poor workmanship had to be the cause, either by intent or by negligence. The Cadweld splicer, according to licensee ;
quality assurance records, had performed over six hundred (600) other !
splices throughout the various Category I buildings and involved both Units 1 and 2. The Cadweld splicer had been terminated in March 1978 for disciplinary reasons not related to his actual wor SUMMARY OF FACTS The following facts were established from licensee quality assurance records made available to the IE Resident Inspector: The failed Cadweld splice was made on the second shift during the evening hours of December 16, 1977, and was one of four (4)
sr Mces made that evening by the splice The splicer had made a total of six hundred eighty-seven (687)
splices over a period beginning January 21, 1977, and terminating March 27, 197 The splicer had been qualified initially and his work inspected and tested commensurate with the requirements of NRC Regulatory Guide 1.10 throughout his working perio a
. .. The licensee / contractor quality control organization had rejected a total of eight (8) splices made by the splicer for visual defects during the above working period, None of twenty-five (25) tensile tests conducted on the splicer's work evidenced failur All but twelve (12) splices made by the splicer were em-bedded in concrete and thus were not readily available for examination. Of the four made on the evening of December 16, only one splice in addition to the failed splice was avail-able for examinatio . The following facts were established by the licensee during the period from October 2 through October 11, 197 The IE Resident Inspector maintained an overview surveillance of these activities during the period: Each of twelve accessible Cadweld splices made by the person in question was radiographed to ascertain position of the bars within 1.he splice sleeve and visually reinspected for correct filler metal fil All splices were deemed acceptable by the license The licensee's Product Assurance Group, a component of the licensee's QA organization charged with special investigations, surevillances, etc., reinspected 3106 Cadwelds in Unit 1 Contain-ment not already embedded with following results:
(1) Nine (9) had visually detectable defects not meeting acceptance criteria. All were tension tested after being removed from the' structure and met acceptance criteri (2) Fifty-one (51) had witness mark problems making uncertain the sleeve centering over the bar ends. Twenty-six(26)
of these were radiographed where the highest degree of uncertainity existed. All were found acceptabl (3) Eight (8) vertical Cadwelds displayed some amount of end packing of asbestos remaining on the bottom end of the splice. Upon removal, all splices were visually acceptabl l l
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. ,, The following facts were established during an interview of the Cad-weld splicer in question at his home on October 7,1978. The inter-view was conducted by the IE Region IV Investigator with the Resident Inspector presen The individual denied any recollection of the specific splice involved although he was shown pictures of the failed elemen The' individual recollected having made a group of splices on the evening of December 16, 197 The individual stated that, in his opinion, he had been a good Cadweld splicer and has never knowingly made a poor splic The individual offered the possibility that' he may not have actually made the failed splice, but rather that another splicer may have used his identifier marking on the splice '
sleeve. The individual could not recall what other splicers may have been in the vicinity that evenin The splicer also offered the possibility that, during his absence, a helper may have improperly set up the Cadweld for him to fire on his return. The individual could not recall the name of the helpe . The following facts were obtained by the IE Resident Inspector during an on-site interview with the Brown & Root quality control inspector of record for the splices made on the evening of Dec-ember 16,1977: There were several other splicers in the general vicinity of the location of the failed splice on the evening of December 1 (The inspection record indicates three other splicers on the sameworksegment.)
, The B&R inspector stated that he recalled the particular work that evening because of the difficulties and hazards involve He stated that much of the splicer setup work was done under poor lighting conditions and that he had had to use a penlight to make his inspection The B&R inspector stated that he had inspected some of the preparatory setup work of each of the splices made that evening by each of the four splice crews involved, but had no recollection of what stage of work he had inspected on j any given splic ,
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CONCLUSIONS The defective splice reported to the IE Resident Inspector as having pulled apart was not representative of the splicer's work and is therefore considered to be an isolated cas . There is no reason to question the integrity of the Cadweld splices in the Containment based upon the licensee's reinspection and test effor : The Cadweld splicers are occasionally careless in proper marking of the spliced bars. The licensee has committed to certain pro-cedural revisions to make clearer the requirements and to retrain-ing'the splicers and their immediate supervision in this are ; The quality control personnel have been remiss in their inspections of Cadweld splices on occasion. The licensee has retrained these personnel during the course of their special inspectio .
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DETAIL 5-1.. ~ Persons Contacted Phincipal Licensee: Personnel '
R.'G. Tolson, TUGC0 Site QA Supervisor J. V.- nawkins, TUGC0/G&H Product: Assurance Superviso R. V. . Fleck, TUGC0/G&H Civil. Inspection Supervisor E. Holland, TUGC0 Product' Assurance Technician 0ther Personnel
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- Cadweld Splicer "CD," Brown & Root Ironworker (No longer employed)
Brown & Root QC~ Inspector
, Unit 1 Containment Wall Reinforcing Steel Cadweld Splice CDD-56 Identification of Incident The licsnsee on October 4,1978, reported a possible significant construction deficiency-to the IE Resident, Inspector. .The li-censee representatives indicated that: a Cadweld splice, identi-fied as.CDD-56.in the Containment wall diagonal reinforcing steel at approximately:the 955' foot level, had pulled apart-during preliminary work of preparing the bar. for additional splicing to continue the steel to the Containment springlin Examination of Cadweld Splice CDD-5 The IE Resident Inspector. examined the splice and found that-one bar, the lower one already embedded in concrete, extended 1 into the splice sleeve only about 1/2 inch rather than the' '
normal of 4-1/2 inches, while the other bar extended through the sleeve to meet the lower'ba The upper bar also had two witness file marks on the bar rib'
for locating the bar ends after splicing. cc.a positioned such as to indicate the actual bar end point and one 4-1/2 inches away indicating where the bar end point should have been, i.e., in the center of the sleeve. The concrete was subse-quently removed from the necessary area of. the lower bar on which two witness file marks were also reveale ,
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Further examination of the splice revealed that the bars had been properly located so as to be substantially concentric with the inside diameter of the splice sleeve and been properly filled with splice filler metal. The finished inplace splice would have met the visual quality control inspection criteria except for the presence of four witness marks instead of two, a point which apparently escaped the notice of the Brown & Root inspector who inspected the splice both before and after it was ,
completed as indicated by applicable inspection record l The IE Resident Inspector reviewed the background of the B&R inspector of record and determined that he had an educational ]
level conmensurate with current industry standards for the ;
job and had received training (with attendant examination) in Cadweld splice inspectio . Interview with B&R QC Inspector On October 12, 1978, the IE Resident Inspector interviewed the B&R inspector for the puprose of ascertaining any peculiar conditions which might have prevailed when the splice was made on December 16, 1977, during the second shift. He was asked if he could give his understanding of the meaning of a check mark and initials on the i inspection record The B&R inspector appeared to very well recollect the particular evening, since it was somewhat unusual. The inspector related that he and several Cadwelders (the record indicates four) with their helpers were dispatched to Unit 1 Containment wall to add short bars to already installed diagonal bars in order to achieve the needed elevation for subsequent concrete placements. These personnel rode a construction elevator up the inside of Contain-ment, crawled over the top of the liner, down Nelson studs on the outside and into place in the reinforcing stee The work was to l take place about 150' above the ground with no scaffolding and only site area lighting availabl The inspector indicated the splice setups were done with the aid of flashlights and that he used a penlight to perform his inspections, a condition which might explain why the extra witness marks were misse l
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The B&R inspector also explained his understanding of the meaning of the check markt on the inspection record. He understood that he was to check the record form if he saw any part of the splice setup of any given splice whereas the related quality control procedure in effect at the time (now superceded and obsolete)
would imply that he observed the entire setup and found it accept-able. The B&R inspector could not recall what setup aspect he observed on any given one of the twelve (12) splices made that (
night although he saw some part of every one and so indicated on )
the recor . Interview with Identified Cadwelder The IE Region IV Investigator and the Resident Inspector jointly interviewed the identified Cadwelder of record involved in making the defective splice to ascertain if he could recall the particular splice or any others made by him or others that might be comparabl The interview took place at the home of the individual on October 7, 1978, rather than on the job site since he had been terminated for disciplinary reasci s not related to his work in March 1978. The l following is a summary of the results of the interview: l The individual denied having any recollection of setting up i a splice in the manner described to him and as illustrated with pictures, The individual could recall splicing the stub extension bars in December 1977 and that the lighting was bad, but did net relate other circumstances, The individual indicated that he thought he had made sixty or seventy diagonal splices for the two units. He further indicated that while the diagonal splices were sometimes more difficult than vertical or horizontal, they were not so difficult as to make him do his job improperly. (Note:
The site records reflect a total of sixty-one such splices, all but two of which have been embedded in concrete for a substantial period.) When asked to guess as to how this could have happened, the individual suggested the possibility that a helper could have done the entire splice setup and that the Cad-welder could have ignited it without first checking the alignmen He did not recall any time when a helper would have done this for hi He could not recall any of his helpers' name _ - _ _ _ _ _ _ _ _ _ _
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. The individual also stated that he might not have made the splice at al Sometimes a Cadwelder_will place another Cadwelder's identifier on a sleeve to' avoid the work in-volved in being tested. This might occue particularly when the splice has to be tested under adverse condition The individual claimed that he had been a good Cadwelder; had always tried to do a good job and never knowingly done improper wor The individual denied any knowledge relative to the double witness marks on the splic . Surveillance of Licensee Evaluation The IE Resident Ins ?ctor maintained general surveillance over the licensee's effort to resubstantiate the quality of Cadweld splicing in the Unit 1 Containment as well as in other building The licensee assigned a quality assurance component referred to as " Product Assurance" to the task. The group had no routine responsibility for making or inspecting Cadwelds but had the necessary expertise to accomplish a re-evaluation. The findings of the group were: The splicer identified as CD had worked in Unit 1 and 2 Containments, the Unit 1 Safeguard Building and the Common Auxiliary Building. Only one of his splices in Unit 1 Containment, other than the failed item, and eleven splices in the Auxiliary Building were not yet embedded in concret These twelve splices were radiographed with a technique suf-ficiently sensitive to reveal the bar positions within the splice sleeve. All were found to be satisfactory. The IE Resident Inspector reviewed selected radiographs including the one splice available in Containment and had no questions concerning this findin The group conducted a preliminary reinspection of other Cad-weld splices in the 955' concrete placement area of the Unit 1 Containment and found problems which caused them to ultimately reinspect all Cadwelds in the structure not yet embedded in concrete. The licensee's records indicate that 3106 such Cad-welds were reinspected by the group of five people over a period of four working day Nine (9) of the splices contained splicing defects which should have been initially rejected by either the craft or by quality control. Each of the nine were cut out and tension teste Each splice developed full bar strengt l
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.s Eight (8) vertical splices had some packi.ng still remaining on the bottom area.
l The balance of visually detectable Cadweld problems were either no witness marks, one witness mark or several marks; i.e., more than two. There were fifty-one splices in this category. The Product Assurance group had twenty-six (26)
of these splices radiographed where there was uncertainity as to correct bar positioning in the sleeve. All were acceptabl ,
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