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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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Text
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- 'o,, UNITED STATES A ,.
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- j NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
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August 4, 1989 Docket Nos. 50-445 and 50-446 Mr. William J. Cahill, Jr.
Executive Vice President, Nuclear Texas Utilities Electric Company 400 North Olive Street, L. B. 81 Dallas, Texas 75201
Dear Mr. Cahill:
SUBJECT:
COMANCHE PEAK SQRT AUDIT A Seismic Qualification Review Team (SQRT) audit of the safety-related electrical and mechanical equipment for Comanche Peak is tentatively scheduled to be perfomed by the NRC staff between August 21 and August 25, 1989. The audit will be conducted using the guidance contained in Regulatory Guide 1.100. Industry Standard IEEE-344-1975, and guidance and acceptance criteria in NUREG-0800, Standard Review Plan (SRP), Section 3.10. The approach in the evaluation for the design adequacy of items from the Equipment Qualification Master List (EQML) will be very similar to the SQRT audit performed in August 1982 at Comanche Peak..
Since 1982, TU Electric has been involved in an extensive corrective action program (CAP), one workscope of which involved equipment qualification. This workscope includes a methodology for correcting generic equipment qualification program deficiencies found by the Comanche Peak Response Team (CPRT). Among these were deficiencies in the identification and classification of require-ments for equipment qualification and in seismic documentation. The NRC staff evaluated the corrective action methodology covered by this workscope and concluded in NUREG-0797 Supplement 19 (SSER 19) that it provides a compre-hensive program for resolving CPRT and staff-identified equipment qualifica-tion issues. SSER 19 states that the adequacy of the program's implementation would be assessed prior to Comanche Peak fuel loading. The upcoming SQRT audit will assess the adequacy of the program's implementation.
The leader of the review team team will be Mr. Jai Rajan of the Mechanical Engineering Branch. He will be assisted by three consultants from EG&G Idaho, Inc.
As a minimum, the audit will include the items listed in the enclosure. o On August 18, 1989, the team will identify three additional items for i
! audit.
TU Electric is requested to submit a completed Seismic Equipment Qualification Summary Package form for each of the items listed in the enclosure by August 9, 1989. The staff has reviewed a copy of TU Electric's sumary package form and found it to be acceptable.
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. Questions:regarding this_ review should be' referred to Jai Rajan at.(301) 492-0917 or.to Melinda Malloy, one of the Comanche Peak project managers at (301) 492-0738.
Should you expect any difficulty in meeting the August 9, 1989 deadline, please inform us.immediately.
Sincerel Christopher I. Grimes, Director Comanche Peak Project Division Office of Nuclear Reactor Regulation
Enclosure:
Equipment List for Audit cc:
See next page 4
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.[ Mr. William J. Cahill, Jr. i cc: . . .
I Asst. Director for Inspec. Programs Roger D. Walker .,
1 Comanche Peak Project Dtvision Manager, Nuclear Licensing p U. S. Nuclear Regulatory Commission Texas Utilities Electric Company l P. O. Box 1029 400 North Olive Street, L.B. 81 Granbury, Texas 76048 Dallas, Texas 75201
' Regional Administrator., Region IV Texas Utilities Electric Company l U. S. Nuclear Regulatory Commission c/o Bethesda Licensing 611 Ryan Flaza Drive, Suite 1000 3 Metro Center, Suite 610 Arlington, Texas 76011 Bethesda, Maryland 20814 Ms. Billie Pirner Garde, Esq. William A. Burchette, Esq.
Garde Law Office Counsel for Tex-La Electric 104 East Wisconsin Avenue Cooperative of Texas ,
Appleton, Wisconsin 54911 Heron, Burchette. Ruckert & Rothwell !
1025 Thomas Jefferson Street, NW l Washington, D.C. 20007 Mrs. Juanita Ellis, President GOS ASSOCIATES, INC.
Citizens Association for Sound Energy Suite 720 1426 South Polk 1850 Parkway Place Dallas, Texas 75224 Marietta, Georgia 30067-8237 E. F. Ottney Jack R. Newman P. O. Box 1777 Newman & Holtzinger Glen Rose, Texas 76043 1615 L Street, NW Suite 1000 Washington, DC 20036 Mr. W. J. Cahill, Jr. Chief, Texas Bureau of Radiation Control Executive Vice President, Nuclear Texas Departraent of Health Texas Utilities Electric Company 1100 West 49th Street 400 No. Olive Street, L.B. 81 Austin, Texas 78756 Dallas, Texas 75201 Honorable George Crump County Judge Glen Rose Texas 76043 l
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! c. = 7 ENCLOSURE COMANCHE PEAK EQUIPMENT FOR ,
3 SEISMIC QUALIFICATION TEAM AUDIT l 1
Package No. Description :
- 1. .SEQSP-ES-0024-01 Solid State Intulation Cabinet by )
Forney Engineering Company j i
- 2. 'SE0SP-MS-0605-01 Main Control Boaro j
.3. SEQSP-ES-0016A-02 Radiation Monitoring Cabinet I
- 4. SEQSP-ES-0011-02 DC Distribution Switch Board !
- 5. SEQSP-ES-0011-03 DC Distribution Panel
- 6. SEQSP-MS-0007-04 AFW Pump Woodward Governor
- 7. SEQSP-MS-0007-02' ' Turbine Driven AFW Pu:np
- 8. . SEQSP-MS-0600-029 24" Fisher Butterfly Valve
- 9. SEQSP-WECM-090, Pressurizer PORV
- 10. 'SEQSP-WEC-0020M Boric Acid Trt.nsfer Pump
- 11. SEQSP-WEC-0075M Positive D!splacement Charging Pump
- 12. SEQSP-WECM-031 2-1/2" RLIJ' Centrifugal Charging Pump
- 13. SEQSP-WEC-0031 Charging Pump 14.. SEQSP-WEC-0032M RHR Pump
'15. SEQSP-WEC-0001M Waste Evaporstor Feed Pump
- 16. SEQSP-WEC-0003M Waste Gas Decay Tank
- 17. SEQSP-WEC-0024M Recycle Holdup Tank Ejector
- 18. SEQSP-APR-01 Auxiliary Relay Rack
- 19. SEQSP-ES-00088 Battery Charger & Circuit Breaker
- 20. SEQSP-MS-0034-31 Cooler
- 21. SEQSP-MS-0034-46 Intercooler
- 22. SEQSP-MS-0076-03 MSIV Bypass Valves
- 23. SEQSP-itS-00158-01 Crane-Deming Fig. 4511 Sump Pumps
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- 24. SEQSP-MS-0034 DeLaval. Diesel Engine 1
- 25. SEQSP MS-0086-01 Posi-Seal 12",150# Trunnion Valve, !'
With Limitorque Actuator I
.26. SEQSP-MS-0022-01 Safeguard System Sequencer
- 27. SEQSP-WEC-0038M. Pressure Safety Valve
- 28. SEQSP-WEC-0089M Air Operated 3-Way Control Valves ;
- 29. SEQSP-WEC-0009M Relief Valve, Type-B r
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Mr. William J. Cahill, Jr. -2 4
Questions regarding this review should be referred to Jai Rajan at (301) 492-0917.
or to Melinda Malloy, one of the Comanche Peak project managers at (301) 492-0738.
Should you expect any difficulty. in meeting the August 9,1989 deadline, please 1 inform us immediately.
Sincerely,
'; Original signed by. ,
Phillip F. McKee '
for Christopher I Grimes, Director Comanche Peak Project Division Office of Nuclear Reactor Regulation "j
Enclosure:
Equipment List for Audit cc:
' See next page Distribution:
Docket File NRC PDR Local PDR-ADSP Reading CPPD Reading D. Crutchfield
- T. Quay C. Grimes P. McKee J. Lycns R. Warnick .
J. H. Wilson
.M. Malloy 1
.M. Fields G. Hubbard O. Rothberg Of*{ i L. Marsh I !
I J. Rajan l C. Vandenburgh j OGC l J. Partlow )
~
E. Jordan B. Grimes /JZwolinski I l
ACRS.(10)
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0FC : :CPPD:NRR :AD:CPPD:NRR :D :NRR :D: : :
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NAME :0Rajan:cb : lalloy ,: Lyons : e :C e : :
....:___.......__:.........s , ...........:_......... .:. ...__ ...:. ...___ ..:....___....
DATE :8/ U/89 :8/8//89
- 8/Y,/89 :8/ T/89 : 8/44,/89 : -
0FFICIAL RECORD COPY l
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