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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
[Table view] |
See also: IR 05000445/1985007
Text
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In Reply Refer To:
Dockets: 50-445/85-07 DEC 30126
50-446/85-05
Texas Utilities Generating Company
ATTN: Mr. W. G. Counsil
Executive Vice President
400 North Olive, L.B. 81
Dallas, Texas 75201
Gentlemen:
Thank you for your letter of April 2,1986, in response to our letter and the
attached Notice of Violation (NOV) dated February:3, 1986., We apologize for
our oversight in not previously acknowledging your response. As a result of
our follow up on the corrective action described in your letter, we. find that
additional information is needed with respect to Items 1,.2.a. and 2.b in the
NOV. ,
Item 1, NOV: We find that the corrective steps taken and results achieved do
not indicate that the installation of the replacement. RTE-Delta Potential
Transformer tiltout assembly was reinspected and accepted. Also, there is no
indication that these deficiencies were documented on a nonconformance report
for Units 1 and 2.
Item 2.a. NOV: The described corrective steps,taken do not indicate whether
a nonconformance report was written for Units 1 and 2. Follow up by the NRC
inspector identified that the drawing which was used for the activity (i.e.,
Westinghouse Drawing 1457F29) had been reviewed and stamped by Gibbs and Hill,
signifying apparent approval of a drawing which allowed use of grout instead
of Class E concrete. Accordingly, it is requested that the stated reason for
the violation be reevaluated, in that the engineering interface or review may
have contributed to causing this violation. Please also identify the design
change authorization, if any, that permits use of grout rather than Class E
concrete in Unit 2, in that the referenced design change DCA-21,179 would
appear to be applicable to Unit 1 only. In your corrective steps to avoid
recurrence, you stated that operational travelers issued during the same time
frame for similar type installations would be reviewed for similar
i
deficiencies. Please clarify how this action is pertinent to precluding
recurrence. Your response also indicated that any corrective actions deemed
nececsary, as a result of this review, would be reported to Region IV by
April 15, 1986. In that no supplementary response has been received by
Region IV, please identify whether or not your review determined corrective
actions were necessary. ,
RIV: SRI
HSPhillips:gb
C/CPRT r d
IBarnes
S /8 7
gHJohnson '
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PDR ADOCK 05000445
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Texas Utilities Generating Company 2
s
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Item 2.b, NOV: With respect to the corrective stens taken, please describe
what formal actions were taken (e.g., specificaticn revision) to justify the
change in output /oltage from 10 1 2v to 12 2v on the revised Westinghouse
Quality Release. Your response also fails to provide any actions taken to
assure that other equipment received from this vendor, irrespective of time
frame, did not exhibit similar documentation deficiencies.
No response was required by our letter of February 3,1986, w'ith respect to
~
Item 2.c of the NOV and we have no further questions with respect to Item 2.d
of the NOV.
Please provide the supplemental information within 20 days of the date of this
letter.
Sincerely,:.{[Of._
od$r. ~;
VG M
E. H. Johnson, Director
Division of Reactor Safety
and Projects
.
cc:
Texas Utilities Electric Company
. ATTN: G. S. Keeley, Manager
Licensing
Skyway Tower
400 North Olive Street
Lock Box 81
Dallas, Texas 75201
Juanita Ellis
President - CASE
- 1426 South Polk Street
,
Dallac, Texas 75224
,
Renea Hicks
Assistant Attorney General
Environmental Protection Division
P. O. Box 12548
Austin, Texas 78711-2548
Administrative Judge Peter Bloch
U.S. Nuclear Regulatory Commission
Washington, D.C. 20555
.
,
.-
Texas Utilities Generating Company 3
-Elizabeth B. Johnson
Administrative Judge
Oak Ridge National Laboratory
.P. O. Box X, Building 3500
Oak Ridge, Tennessee 37830
Dr. Kenneth A. McCollom
1107 West Knapp
Stillwater, Oklahoma 74075
Dr. Walter H. Jordan
881 Outer Drive
Oak Ridge, Tennessee 37830
Anthony Roisman, Esq.
Executive Director
Trial Lawyers .for Public Justice _.
2000 P. Street, N.W. Suite 611
-Washington, D.C. 20036
Texas Radiation Control Program Director
bec to DMB (IE01) .
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bcc distrib. by RIV: '
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- RRI-0PS -*RSTS Operator - ,
.
- T. F. Westerman, RSB DRSP ;
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V. Noonan, NRR R. Martin, RA -
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L. Chandler, 0GC *RSB . -
J. Taylor, IE
- D. We':s, RM/ALF J. Conklin, IE
- I. Basiias, CPTG * Project Inspector ,
. .
- Log # TXX-4727
-
File # 10130
IR 85-07
,
TEXAS UTILITIES GENERATING COMPANY 85-05
9 anywAv vowra . .oo noans ouvz svarer. a m. si . DAW.AN. TEXAS Maos
April 2, 1986
_ _ _ . -
EIIMJAf?JE*A L,
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Mr. Eric H. Johnson, Director
Division of Reactor Safety and Projects q{ l . ,, g g
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U. S. Nuclear Regulatory Commission i'~.. J. !
611 Ryan Plaza Drive, Suite 1000 OL - g
Arlington, Texas 76012 _. -
SUBJECT: COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446
RESPONSE TO NRC NOTICE OF VIOLATION
INSPECTION REPORT NOS.: 50-445/85-07 AND 50-446/85-05
Dear Mr. Johnson:
We have reviewed your letter dated February 3, 1986, concerning the inspec-
tion conducted by Messrs. J. E. Cummins, H. S. Phillips, and others during
the period April 1, 1985, through June 21, 1985. This inspection covered
activities authorized by NRC Construction Permits CPPR-126 and CPPR-127 for
Comanche Peak Steam Electric Station Units 1 and 2.
We requested and received a two week extension in providing our response
during a telephone discussion on March 6, 1986. We requested and received
a second two week extension on March 19, 1986.
We have responded to the Notice of Viclation in the attachments to this
letter. We have attached the Notice of Violation to aid in understanding
l our response.
Very truly yours,
V llV/l^
W. G. Counsil
l JWA/ arm
,
! Attachments i
c- Region IV (Original + 1 copy)
l
Director, Inspection and Enforcement (15 copies) '
U. S. Nuclear Regulatory Commission
Washington, D.C. 20555
Mr. V. S. Noonan
Mr. D. L. Kelley
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A onnsox or nexAs unLn1ES ELECTRIC CoMPAhT
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APPENDIX A
NOTICE OF VIOLATION
Texas Utilities Electric Company Docket: 50-445/85-07
Comanche Peak Steam Electric Station 50-446/85-05
Units 1 and 2 Permit: CPPR-126
CPPR-127
During an NRC inspection conducted on April 1 through June 21, 1985, violations
of NRC requirements were identified. In accordance with the " General Statement
of Policy and Procedures for NRC Enforcement Actions," 10 CFR Part 2,
Appendix C (1985), the violations are listed below:
1. Failure to Promptly Correct an Identified Problem with RTE - Delta
.
Potential Transformer Tiltout Subassemblies
10 CFR 50, Appendix B, Criterion XVI, as implemented by Texas Utilities
Generating Company (TUGCO) Quality Assurance Plan (QAP), Section 16.0,
Revision 0, requires that measures shall be established to assure that
conditions adverse to quality, such as failures, malfunctions, deficien-
cies deviations, defective material and equipment, and nonconformahces are
promptly identified and corrected.
Contrary to the above, a potential problem with RTE - Delta potential
transformer tiltout subassemblies, which are used in the emergency diesel
generator control panels, was identified to the applicant via a letter,
dated June 15, 1983, from Transamerica Delaval Inc. This letter also
provided instructions for correcting the potential problem. However, the
applicant did not take the corrective action. The NRC initially reported
this item as unresolved in NRC Inspection Report 50-445/84-40.
This is a Severity Level IV violation. (Supplement II.E) (445/8507-01
446/8505-01).
2. Failure To Follow Procedures
l
10 CFR Part 50, Appendix B, Criterion V, as implemented by the TUGC0 QAP,
l
Section 5.0, Revision 2 requires that activities affecting quality shall
be prescribed by documented instructions, procedures, or drawings, of a
type appropriate to the circumstances and shall be accomplished in accor-
dance with these instructions, procedures, or drawings.
I a. Drawing 2323-51-0550, Revision 4, Section 6-6 specified the use of
l Class E" concrete for the Unit I reactor coolant pump and steam
i generator supports.
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Contrary to the above, commercial nonshrink grout was used to grout
' the Unit I reactor coolant pump and steam generator supports in lieu
of Class "E" concrete. (445/8507-02)
This is a Severity Level V violation (Supplement II.E).
b. Brown and Root Procedure QI-QAP-7.2-8, " Receiving of Westinghouse
Safety Related Equipment," Section 3.1.d.1, requires a QC inspector
to verify that the Westinghouse Quality Release (QR) document -
checklist items be filled out completely and accurately.
Contrary to the above, the voltage recorded on Westinghouse QR 41424
checklist, attachment 1, step 4.1, was outside the specified
'; tolerance, but the QC receipt inspector accepted QR as satisfactory.
(445/8507-03)
.
This is a Severity' Level IV violation,
c. Brown & Root Procedure 35-1195-CCP-10. Revision 5, dated December 4,
1978, requires that central and truck mixer blades be checked
quarterly to assure that mixer blade wear does not exceed a loss of
i
10% of original blade height.
Contrary to the above, on May 31, 1985, the NRC inspector determined
that there was no objective evidence (records) that the mixing blades
,
had been inspected quarterly since the trucks were placed in service
l in 1977. (445/8507-04; 446/8505-02)
i
This is a Severity Level V violation (Supplement II.E)
d. Brown & Root Procedure CP-QAP-15.1, " Field Control of Nonconforming
Item, " states that nonconforming conditions shall be documented in a
Deficiency and Disposition Report (DDR). Procedure CP-QCP-1.3, " Tool
l Equipment Calibration and Control," dated July 14, 1975, states that
out-of-calibration equipment shall be identified on a DDR.
Contrary to the above, on May 31, 1985, the NRC inspector reviewed
the calibration file for scale (MTE 779) used for weighing cement and
found that a 24-48 pound deviation from the required accuracy was
encountered with the water and cement scales during a 1975 calibration
of the backup plant scales, however, no DDR was issued to identify
this condition and require disposition of the scale and concrete (if
any) produced. (445/8507-06;446/8505-04).
,
l
This is a Severity Level IV violation (Supplement II.E).
.
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Pursuant to the provisions of 10 CFR 2.201, Texas Utilities Electric Company is
hereby required to submit to this office within 30 days of the date of the
letter transmitting this Notice, a written statement or explanation in reply,
including for each violation: (1) the reason for the violations if admitted,
2) the corrective steps which have been taken and the results achieved,
3) the corrective steps which will be taken to avoid further violations, and
4) the date when full compliance will be achieved. Where good cause is shown,
consideration will be given to extending the response time.
Dated at Arlington, Texas,
this 3rd day of February,1986
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Response to Notice of Violation
Item 1 (445/8507-01 and 446/8505-01)
'.
1.
Reason for Violation:
The violation relates to a Part 21 notice provided by a CPSES diesel
generator subtier supplier (RTE-Delta) in June 1983.
The violation is
the 21
Part result of two unrelated administrative oversights
notice. in handling the
when
the subjectaPart "potentially"
21 notice. reportable deficiency was ca i
The second administrative oversight
involved omission of tne issue when a program was conducted in mid 19
to assure
issues. corrective actions were accomplished for prior Part 21
2.
Corrective Steps Taken and Results Achieved:
work permits Z-2912 and'Z-2914 in December 1984. Action
were identified by master Data Base Item Unit 2 activities
and completed in August of 1985. 3003-31 (issued January 1985)
response to an NRC open item (445/8440-02).These actions were initiated in
3.
Corrective Steps to Avoid Recurrence:
In response to an earlier NRC open item (445/8407-01), programmatic
measures were established
actions related to Part 21 issues.
in mid 1984 to positively control corrective
notices as "potentially" reportable deficiencies purs
10CFR50.55(e).
governed by TUGC0 Corporate Procedure NEO-CS-1, " E
Reporting of Items / Events under 10CFR21 and 10CFR50.55(e)."
The oversight of the specific (RTE-Delta) Part 21 notice during the mid
1984 review is considered to be isolated. The failure to recognize
this issue
different was the result of the same identifier being assigned to two
items.
(445/8440-01). This was the subject of a previous violation
during our review of the earlier violation.No other instance of a similar na
4. Date When in Full Compliance:
Programmatic measures were established in mid 1984 to
control corrective actions related to Part 21 issues. positively '
cific
in Augustfindings
1985. related to the RTE-Delta Part 21 notice were correctedAll of t
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- . Response to Notice of Violation
,'
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Item 2(a) (445/8507-02)
k 1. Reason for Violation:
The violation is the result of a failure on the part of personnel pre-
paring work control documents to properly recognize the hierarchy of
design documents. Specifically, when design and vendor installation
documents differ, the design document establishes precedent.
Although consistent with the requirements of the vendor drawing (W
Drawing 1457F29), the use of non-shring commercial grout was contrary
to the requirements of the design drawing (2323-51-0550). The design
drawing specified the use of class "E" concrete. The use of grout as
an acceptable design alternative should have been properly documented
by design change prior to the placement.
2. Corrective Steps Taken and Results Achieved:
Based upon a review of the grout card (No. 186 issued November 1981)
and the results of the compressive strength test for the grout used in
this application, a design change (DCA-21, 179) was issued November 8,
1984, to document acce~tance
p of the installation.
3. Corrective Steps to Avoid Recurrence:
Operational travelers (work control documents) for similar type
installations issued during the same time frame as the installation
identified in the violation will be reviewed for similar deficiencies.
Results of the review will be completed by April 4, 1386.
Although we believe the specific finding is an isolated case, a project
directive will be issued re-emphasizing:
0 the requirements of properly documenting design
alternatives prior to initiating construction activities,
O the precedence of design vs. vendor documents.
4. Date When in Full Compliance:
Any corrective actions deemed necessary based on the results of the
(Item 3) review will be reported by April 15, 1986, to Region IV. The
project directive will be issued by April 15, 1986.
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. - Response to Notice of Violation
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Item 2(b) (445/8507-03)
. 1. Reason for Violation:
,
The out-of-tolerance condition was not detected by receiving inspection
when reviewing the data package.
2. Corrective Steps Taken and Results Achieved:
Receiving inspection reports issued in same time frame as the receipt
of the equipment in question, were reviewed for similar oversight. No
deficiencies were noted. Westinghouse QRN-41424 Rev. I was added to
receiving inspection report package to identify the change in output
values.
3. Corrective Steps to Avoid Recurrence:
Construction receiving inspection personnel were retrained in reviewing
receiving inspection documentation packages.
4. Date When in Full Compliance:
February 27, 1986.
. __. - - . _ . _ ._. -- _ . _ - . _
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m "o Response to Notice of Violation-
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Item 2(c) (445/8507-04 and 446/8505-02)
.
.
i A reply to this notice of violation is not required as noted in the NRC
Region IV letter of February 3, 1986 (E.H. Johnson to W.G. Counsil)
J
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.~ Response to Notice of Violation
Item 2(d) (445/8507-06 and 446/8505-04)
.
P
1. Reason for Violation:
A review of the historical procedures files has indicated that the
majority of project procedures controlling safety related work, and
programmatic requirements were not issued until or after 7/14/75.
Although project practice at this early stage of construction was to
defer safety related work until the appropriate implementing and sup-
port procedures were issued and distributed, the established control
was inadequate in this instance.
2. Corrective Steps Taken and Results Achieved:
Concrete pour records were reviewed to determine which category I place-
ments were made during the subject calibration interval.
Nonconformance reports (NCR-C-85-101882 R. 1 issued 11/26/85
NCR-C-85-201617 R.1 issued 11/27/85) were initiated to document the two
placements made. Engineering dispositioned these NCR's basing the
decision on the design _ cylinder compressive results. These NCR's were
closed in December 1985.
3. Corrective Steps to Avoid Recurrence:
The site procedures controlling these activities and the associated
programmatic requirements, were issued onsite after the discrepancy
identified by the inspector had occurred and prior to the next sche-
duled calibration. These procedures provided the necessary controls
for handling nonconforming items, implemented a detailed calibration
program and required auditing the effectiveness of the established
10CFR50 Appendix B Quality Program requirements; continuing periodic
audits by TUGCO, Brown & Root, and third parties have insured accep-
table implementation of the controlled measuring and testing equipment
calibration program. This appears to be an isolated instance since
review of pour cards during this time period did not identify any
safety related placements other than those addressed above. Safety
related mechanical and electrical activities had not yet commenced.
4. Date When in Full Compliance:
CPSES is currently in full compliance with 10CFR50 Appendix 8 Criterion
XII.
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