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Category:CORRESPONDENCE-LETTERS
MONTHYEARTXX-9924, Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span1999-10-22022 October 1999 Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span ML20217M5711999-10-20020 October 1999 Forwards Insp Repts 50-445/99-15 & 50-446/99-15 on 990822- 1002.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy TXX-9923, Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred1999-10-15015 October 1999 Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred ML20217E7951999-10-12012 October 1999 Forwards COLR for Unit 1,Cycle 8,per TS 5.6.5 ML20212L2891999-10-0101 October 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals. Purpose of GL Was to Obtain Info That Would Enable NRC to Verify That Condition of Licensee SG Internals Comply with Current Licensing Bases TXX-9922, Forwards Revised COLR, for Cycle 5 for Unit 21999-10-0101 October 1999 Forwards Revised COLR, for Cycle 5 for Unit 2 ML20216J5571999-10-0101 October 1999 Provides Final Response to GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps ML20212G0721999-09-24024 September 1999 Forwards Rev 4 to Augmented Inservice Insp Plan for CPSES, Unit 1. Future Changes & Revs to Unit 1 Augmented Inservice Insp Plan Will Be Available on Site ML20212H0461999-09-24024 September 1999 Forwards Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 990820 ML20212F7481999-09-24024 September 1999 Forwards SER Authorizing Relief from Exam Requirement of 1986 Edition ASME Code,Section XI Pursuant to 10CFR50.55a(a)(3)(ii) for Relief Request A-3 & 10CFR50.55a(g)(6)(i) for Relief Requests B15,16,17 & C-4 ML20212F1041999-09-23023 September 1999 Requests That NRC Be Informed of Any Changes in Scope of Y2K System Deficiencies Listed or Util Projected Completion Schedule for Comanche Peak Steam Electric Station,Units 1 & 2 ML20212E6661999-09-21021 September 1999 Advises That Info Contained in Application & Affidavit, (CAW-99-1342) Re WCAP-15009,Rev 0, Comache Peak Unit 1 Evaluation for Tube Vibration Induced Fatigue, Will Be Withheld from Public Disclosure ML20212D9111999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of CPSES & Did Not Identify Any Areas in Which Performance Warranted Insp Beyond Core Insp Program.Core Insp Plan at Facility Over Next 7 Months.Insp Plan Through March 2000 Encl ML20212A7601999-09-14014 September 1999 Forwards Insp Repts 50-445/99-14 & 50-446/99-14 on 990707-0821.Four Violations Occurred & Being Treated as Ncvs.Conduct of Activities Was Generally Characterized by safety-conscious Operations & Sound Radiological Controls TXX-9921, Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC1999-09-10010 September 1999 Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC ML20211P3761999-09-0707 September 1999 Ack Receipt of Ltr Dtd 990615,transmitting Rev 30 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20211L9871999-09-0303 September 1999 Forwards Rev 31 to Technical Requirements Manual. All Changes Applicable to Plants Have Been Reviewed Under Util 10CFR50.59 Process & Found Not to Include Any USQs TXX-9915, Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl1999-09-0303 September 1999 Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl ML20211K2231999-08-31031 August 1999 Forwards Txu Electric Comments of Rvid,Version 2 ML20211J3801999-08-27027 August 1999 Forwards Corrected TS Page 3.8-26 to Amend 66 to Licenses NPF-87 & NPF-89,respectively.Footnote on TS Page 3.8-26 Incorrectly Deleted ML20211G7301999-08-26026 August 1999 Forwards Revs 29 & 30 to CPSES Technical Requirements Manual (Trm). Attachments 1 & 2 Contain Description of Changes for Revs 29 & 30 Respectively ML20211G1081999-08-26026 August 1999 Responds to NRR Staff RAI Re Util Mar 1999 Submittal for NRC Review & Approval of Changes to CPSES Emergency Classification Procedure ML20211G3441999-08-25025 August 1999 Forwards Response to NRC RAI on LAR 98-010 for Cpses,Units 1 & 2.Communication Contains No New Licensing Commitments Re Cpses,Units 1 & 2 ML20211B2861999-08-18018 August 1999 Forwards Insp Repts 50-445/99-13 & 50-446/99-13 on 990720- 23.No Violations Noted.Insp Included Implementation of Licensee Emergency Plan & Procedures During Util Biennial Emergency Preparedness Exercise ML20211C4661999-08-18018 August 1999 Discusses Proprietary Info Re Thermo-Lag.NRC Treated Bisco Test Rept 748-105 as Proprietary & Withheld It from Public Disclosure,Iaw 10CFR2.790 ML20210U3981999-08-17017 August 1999 Forwards Monthly Operating Repts for July 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs or SVs for Plant Occurred ML20211C0991999-08-17017 August 1999 Forwards Rev 3 to ASME Section XI ISI Program Plan,Unit 2 - 1st Interval, Replacing Rev 2 in Entirety ML20211C4571999-08-16016 August 1999 Forwards Omitted Subj Page of Contractor TER TXX-9919, Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 9908021999-08-16016 August 1999 Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 990802 ML20210R6561999-08-13013 August 1999 Forwards Response to NRR 990805 Telcon RAI Re License Amend Request 98-010,to Increase Power for Operation of CPSES Unit 2 to 3445 Mwth & Incorporating Addl Changes Into Units 1 & 2 TS ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210S6411999-08-12012 August 1999 Informs That Wg Guldemond,License SOP-43780,is No Longer Performing Licensed Duties.Discontinuation of License Is Requested ML20210R2221999-08-12012 August 1999 Forwards Insp Repts 50-445/99-10 & 50-446/99-10 on 990510-0628.Violations Noted & Being Treated as Ncvs, Consistent with App C of Enforcement Policy ML20210N1101999-08-0404 August 1999 Provides Supplemental Info to Util 990623 License Amend Request 99-005 Re Bypassing DG Trips.Info Replaces Info Contained in Subject Submittal in Attachment 2,Section II, Description of TS Change Request ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210J2301999-08-0202 August 1999 Forwards Amend 96 to CPSES Ufsar.Replacement of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,Rev 2 ML20210J6071999-08-0202 August 1999 Forwards line-by-line Descriptions of Changes in Amend 96 to CPSES UFSAR Transmitted by Util Ltr TXX-99166,dtd 990802. Replacment of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,rev 2 TXX-9916, Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 9907271999-08-0202 August 1999 Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 990727 TXX-9918, Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-9906301999-08-0202 August 1999 Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20210K2321999-07-29029 July 1999 Forwards Insp Repts 50-445/99-12 & 50-446/99-12 on 990530-0710.No Violations Noted ML20210G5861999-07-29029 July 1999 Forwards fitness-for-duty Program Performance Data for Six Month Period of Jan-June 1999 ML20210J0121999-07-27027 July 1999 Forwards Summary of Methodology for Determination of NDE Measurement Uncertainty,In Response to Recent Discussions with NRC Re LAR 98-006 Concerning Rev to SG Tube Plugging Criteria TXX-9917, Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES1999-07-26026 July 1999 Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES ML20210F3121999-07-26026 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, ML20210D8231999-07-23023 July 1999 Forwards Safety Evaluation of Relief Requests Re Use of 1998 Edition of Subsections IWE & Iwl of ASME Code for Containment Insp ML20210D3211999-07-21021 July 1999 Provides List of Estimates of Licensing Actions,In Response to Administrative Ltr 99-02,dtd 990603 ML20210C2931999-07-21021 July 1999 Supplements 880323 Response to NRC Bulletin 88-02, Rapidly Propagating...Sg Tubes, Non-proprietary WCAP-15010 & Proprietary Rev 0 to WCAP-15009, CP Unit 1 Evaluation for Tube Vibration... Encl.Proprietary Rept Withheld ML20209H0111999-07-16016 July 1999 Forwards Relief Request C-4 to CPSES Unit 2 ISI Program for Approval ML20210C3331999-07-16016 July 1999 Forwards Exam Repts 50-445/99-301 & 50-446/99-301 on 990618- 24.Exam Included Evaluation of Six Applicants for Senior Operator Licenses ML20209H2551999-07-16016 July 1999 Forwards ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2 & Containment ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2,per ASME Boiler & Pressure Vessel Code,Section Xi,Paragraph IWA-6230 1999-09-07
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARTXX-9924, Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span1999-10-22022 October 1999 Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span TXX-9923, Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred1999-10-15015 October 1999 Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred ML20217E7951999-10-12012 October 1999 Forwards COLR for Unit 1,Cycle 8,per TS 5.6.5 ML20216J5571999-10-0101 October 1999 Provides Final Response to GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps TXX-9922, Forwards Revised COLR, for Cycle 5 for Unit 21999-10-0101 October 1999 Forwards Revised COLR, for Cycle 5 for Unit 2 ML20212G0721999-09-24024 September 1999 Forwards Rev 4 to Augmented Inservice Insp Plan for CPSES, Unit 1. Future Changes & Revs to Unit 1 Augmented Inservice Insp Plan Will Be Available on Site ML20212H0461999-09-24024 September 1999 Forwards Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 990820 TXX-9921, Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC1999-09-10010 September 1999 Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC ML20211L9871999-09-0303 September 1999 Forwards Rev 31 to Technical Requirements Manual. All Changes Applicable to Plants Have Been Reviewed Under Util 10CFR50.59 Process & Found Not to Include Any USQs TXX-9915, Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl1999-09-0303 September 1999 Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl ML20211K2231999-08-31031 August 1999 Forwards Txu Electric Comments of Rvid,Version 2 ML20211G1081999-08-26026 August 1999 Responds to NRR Staff RAI Re Util Mar 1999 Submittal for NRC Review & Approval of Changes to CPSES Emergency Classification Procedure ML20211G7301999-08-26026 August 1999 Forwards Revs 29 & 30 to CPSES Technical Requirements Manual (Trm). Attachments 1 & 2 Contain Description of Changes for Revs 29 & 30 Respectively ML20211G3441999-08-25025 August 1999 Forwards Response to NRC RAI on LAR 98-010 for Cpses,Units 1 & 2.Communication Contains No New Licensing Commitments Re Cpses,Units 1 & 2 ML20210U3981999-08-17017 August 1999 Forwards Monthly Operating Repts for July 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs or SVs for Plant Occurred ML20211C0991999-08-17017 August 1999 Forwards Rev 3 to ASME Section XI ISI Program Plan,Unit 2 - 1st Interval, Replacing Rev 2 in Entirety TXX-9919, Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 9908021999-08-16016 August 1999 Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 990802 ML20210R6561999-08-13013 August 1999 Forwards Response to NRR 990805 Telcon RAI Re License Amend Request 98-010,to Increase Power for Operation of CPSES Unit 2 to 3445 Mwth & Incorporating Addl Changes Into Units 1 & 2 TS ML20210S6411999-08-12012 August 1999 Informs That Wg Guldemond,License SOP-43780,is No Longer Performing Licensed Duties.Discontinuation of License Is Requested ML20210N1101999-08-0404 August 1999 Provides Supplemental Info to Util 990623 License Amend Request 99-005 Re Bypassing DG Trips.Info Replaces Info Contained in Subject Submittal in Attachment 2,Section II, Description of TS Change Request TXX-9918, Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-9906301999-08-0202 August 1999 Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20210J2301999-08-0202 August 1999 Forwards Amend 96 to CPSES Ufsar.Replacement of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,Rev 2 ML20210J6071999-08-0202 August 1999 Forwards line-by-line Descriptions of Changes in Amend 96 to CPSES UFSAR Transmitted by Util Ltr TXX-99166,dtd 990802. Replacment of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,rev 2 TXX-9916, Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 9907271999-08-0202 August 1999 Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 990727 ML20210G5861999-07-29029 July 1999 Forwards fitness-for-duty Program Performance Data for Six Month Period of Jan-June 1999 ML20210J0121999-07-27027 July 1999 Forwards Summary of Methodology for Determination of NDE Measurement Uncertainty,In Response to Recent Discussions with NRC Re LAR 98-006 Concerning Rev to SG Tube Plugging Criteria TXX-9917, Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES1999-07-26026 July 1999 Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES ML20210F3121999-07-26026 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, ML20210C2931999-07-21021 July 1999 Supplements 880323 Response to NRC Bulletin 88-02, Rapidly Propagating...Sg Tubes, Non-proprietary WCAP-15010 & Proprietary Rev 0 to WCAP-15009, CP Unit 1 Evaluation for Tube Vibration... Encl.Proprietary Rept Withheld ML20210D3211999-07-21021 July 1999 Provides List of Estimates of Licensing Actions,In Response to Administrative Ltr 99-02,dtd 990603 ML20209H2551999-07-16016 July 1999 Forwards ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2 & Containment ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2,per ASME Boiler & Pressure Vessel Code,Section Xi,Paragraph IWA-6230 ML20209H0111999-07-16016 July 1999 Forwards Relief Request C-4 to CPSES Unit 2 ISI Program for Approval ML20209G0721999-07-13013 July 1999 Forwards Monthly Operating Repts for June 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs of SV Occurred During Reporting Period ML20209F0681999-07-0909 July 1999 Informs That Effective 990514,TU Electric Formally Changed Name to Txu Electric.Change All Refs of TU Electric to Txu Electric on Correspondence Distribution Lists ML20209E0421999-07-0909 July 1999 Forwards Response to NRC Request for Addl Info on LAR 98-010.Attachment 1 Is Affidavit for Info Supporting LAR 98-010 ML20209B6021999-06-30030 June 1999 Submits Second Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Readiness Disclosure for Reporting Status of Facility Y2K Readiness Encl ML20195J6981999-06-15015 June 1999 Provides Addl Info Related to Open Issue,Discussed in 990610 Conference Call with D Jaffe Re ISI Program Relief Request L-1 Submitted by Util on 980220 ML20196A4921999-06-15015 June 1999 Forwards Rev 30 to Physical Security Plan.Rev Withheld,Per 10CFR73.21 ML20195J0491999-06-14014 June 1999 Submits Response to RAI Re Implementation of 1.0 Volt Repair Criteria ML20195J0651999-06-14014 June 1999 Submits Response to RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves 05000445/LER-1999-001, Forwards LER 99-001-00, Some Electrical Contacts for RCS Pressure Relief Valves Were Not Included in Surveillance Testing Procedures. New Licensing Commitments Identified in Attachment 11999-06-0808 June 1999 Forwards LER 99-001-00, Some Electrical Contacts for RCS Pressure Relief Valves Were Not Included in Surveillance Testing Procedures. New Licensing Commitments Identified in Attachment 1 ML20195F0091999-06-0808 June 1999 Forwards Response to RAI Re Units 1 & 2 ISI Program for Relief Requests E-1 & L-1.Communication Contains No New Licensing Basis Commitments Re Cpses,Units 1 & 2 ML20207E1921999-05-28028 May 1999 Submits Updated Request for NRC Staff to Review & Approve Certain Changes to CPSES Emergency Plan Submitted in 981015 & s Prior to Changes Being Implemented at CPSES ML20207E1711999-05-28028 May 1999 Supplements 990526 LAR 99-004 as TU Electric Believes Extingency Exists in That Proposed Amend Was Result of NOED Granted to Prevent Shudown of CPSES Unit 1 ML20207D9841999-05-26026 May 1999 Requests That NRC Exercise Enforcement Discretion to Allow Cpses,Unit 1 to Remain in Mode 1,power Operation,Without Having Performed Svc Test,Per SR 4.8.2.1d on Unit 1 Battery BT1ED2 ML20195B6351999-05-25025 May 1999 Submits Response to RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves TXX-9912, Forwards Txu Electric (Formerly TU Electric) CPSES Emergency Preparedness Exercise Scenario Manual for 990721-22,Graded Exercise1999-05-21021 May 1999 Forwards Txu Electric (Formerly TU Electric) CPSES Emergency Preparedness Exercise Scenario Manual for 990721-22,Graded Exercise ML20206U1981999-05-20020 May 1999 Forwards Form 10K Annual Rept,Per 10CFR50.71(b). Communication Contains No New Licensing Basis Commitments Re Cpses,Units 1 & 2 ML20196L1931999-05-20020 May 1999 Forwards MOR for Apr 1999 for Cpses,Units 1 & 2.During Reporting Period There Have Been No Failures or Challenges to Power Operated Relief Valves or Safety Valves TXX-9911, Forwards non-proprietary & Proprietary Responses to RAI Re LAR 98-010 by Incorporating Attached Changes Into CPSES Unit 2 OL NPF-89 & CPSES Units 1,OL NPF-87 & 2 TS to Increase Licensed Power.W & Caldon Proprietary Responses Withheld1999-05-14014 May 1999 Forwards non-proprietary & Proprietary Responses to RAI Re LAR 98-010 by Incorporating Attached Changes Into CPSES Unit 2 OL NPF-89 & CPSES Units 1,OL NPF-87 & 2 TS to Increase Licensed Power.W & Caldon Proprietary Responses Withheld 1999-09-03
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059K6141990-09-17017 September 1990 Submits Documentation of 900906 Telcon Re Addl Util Candidate for Licensed Operator Generic Fundamentals Exam Section ML20059G8761990-09-10010 September 1990 Forwards Rev 8 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML20059F8461990-09-0404 September 1990 Responds to NRC Re Violations Noted in Insp Repts 50-445/90-22 & 50-446/90-22 on 900606-0705.Corrective action:OPT-467A Changed to Provide Addl Prerequisite Info Re Solid State Protection Sys Switch Lineup During Testing ML20059E4981990-08-31031 August 1990 Forwards Revised Radial Peaking Factor Limit Rept for Cycle 1 Per Tech Specs Through Amend 1 & ML20059E4201990-08-30030 August 1990 Forwards Objectives & Guidelines for 1990 Emergency Preparedness Exercise Scheduled for 901113 ML20028G8281990-08-29029 August 1990 Forwards Comanche Peak Unit 1 Semiannual Radioactive Effluent Release Rept,900403-0630 & ODCM TXX-9030, Forwards Endorsements 40 & 4 to Nelia Policy NF-274 & Maelu Policy M-90,respectively & Endorsements 10,11,12,13,14 & 15 to Maelu Policy MF-1311990-08-27027 August 1990 Forwards Endorsements 40 & 4 to Nelia Policy NF-274 & Maelu Policy M-90,respectively & Endorsements 10,11,12,13,14 & 15 to Maelu Policy MF-131 ML20059F4381990-08-23023 August 1990 Forwards Public Version of Revised Emergency Plan & Corporate Emergency Response Procedures,Consisting of Rev 1 to EPP-313,Rev 7 to CERP-101,Rev 7 to CERP-102 & Revised Forms.W/Dh Grimsley 900906 Release Memo TXX-9029, Responds to NRC Re Violations Noted in Insp Repts 50-445/89-57 & 50-446/89-57.Corrective Actions:Storage Facilities for Instrumentation & Control Work Packages Improved to Provide Acceptable Protection for Documents1990-08-20020 August 1990 Responds to NRC Re Violations Noted in Insp Repts 50-445/89-57 & 50-446/89-57.Corrective Actions:Storage Facilities for Instrumentation & Control Work Packages Improved to Provide Acceptable Protection for Documents ML20058P0571990-08-13013 August 1990 Forwards, Comanche Peak Steam Electric Station Unit 1 Control Room Simulator 10CFR55 Certification Initial Rept ML20058N2311990-08-0909 August 1990 Forwards First Half 1990 fitness-for-duty Program Performance Data,Per 10CFR26.71(d).Point of Contact for Personnel,Random Testing Program Results & Confirmed Positive Tests Summary & Mgt Summary Included in Data ML20059A5831990-08-0404 August 1990 Responds to Info Request Made During 900802 Meeting Re Inadvertent Safety Injections on 900726 & 30 & Results of 100% Power Plateau Testing TXX-9024, Provides Status of Exam Activity & Revised Completion Schedule for Portion of Exam.Util Deferred Preoperational Testing of Facility Spent Fuel Pool Cooling & Cleanup Sys Until Prior to First Off Loading of Spent Fuel1990-08-0303 August 1990 Provides Status of Exam Activity & Revised Completion Schedule for Portion of Exam.Util Deferred Preoperational Testing of Facility Spent Fuel Pool Cooling & Cleanup Sys Until Prior to First Off Loading of Spent Fuel TXX-9022, Forwards Detailed Descriptions of Changes in Amend 79 to FSAR for Comanche Peak Steam Electric Station1990-07-31031 July 1990 Forwards Detailed Descriptions of Changes in Amend 79 to FSAR for Comanche Peak Steam Electric Station TXX-9027, Responds to NRC Re Violations Noted in Insp Repts 50-445/90-19 & 50-446/90-19.Corrective Action:Specific Activity within Tech Spec Limits.No Further Corrective Action Required1990-07-30030 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-445/90-19 & 50-446/90-19.Corrective Action:Specific Activity within Tech Spec Limits.No Further Corrective Action Required ML20055J1571990-07-27027 July 1990 Submits Info Re Replacement of Borg-Warner/Intl Pump,Inc Check Valve Swing Arms,Per .Swing Arms in ASME Code Class 2 Check Valves Will Be Replaced During First Refueling Outage ML20056A0461990-07-24024 July 1990 Requests Regional Waiver of Compliance for Containment Pressure Transmitter 1-PT-934 During Coming Outage TXX-9023, Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. No Subj Transmitters in Existence at Facility1990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. No Subj Transmitters in Existence at Facility ML20055G6351990-07-17017 July 1990 Submits Results of Remote Shutdown Panel Environ Survey ML20055F9391990-07-13013 July 1990 Advises That Operators Have Gained Significant Experience in Operating Plant Under Wide Range of Conditions & Have Demonstrated Necessary Proficiency to Safely Operate Unit ML20055F9371990-07-13013 July 1990 Submits Info Re Revised Acceptance Criteria for THERMO-LAG Fire Barrier,Per 900705 Telcon.On Exposure to Heat Flux at Surface of Barrier,Listed Mechanisms Activated.Fire Testing Demonstrates That Panels Qualified W/Variation in Thickness ML20044A7001990-06-26026 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Util Will Implement for Unit 2 Activities Performed for Unit 1 ML20044A1411990-06-20020 June 1990 Forwards Endorsements 4 & 5 to Nelia Certificate N-90, Endorsements 5 & 6 to Maelu Certificate M-90 & Endorsements 34,35,36,37,38 & 39 to Nelia Policy NF-274 ML20043H7031990-06-18018 June 1990 Discusses Mod/Rework to Auxiliary Feedwater Sys Check Valves Mfg by Bw/Ip Intl,Inc.All But One Affected Check Valve modified.Motor-driven Auxiliary Feedwater Pump Discharge Valve Check Valve Body Replaced ML20043H2181990-06-15015 June 1990 Forwards Response to 900515 Request for Addl Info on Emergency Preparedness.Ongoing Emergency Preparedness Programs Address Concerns Raised by Citizens for Fair Util Regulation ML20043G3131990-06-15015 June 1990 Forwards Addl Info Re Pressurizer Surge Line Thermal Stratification & leak-before-break Evaluation & Nonproprietary Suppl 3 to WCAP-12247, Supplementary Assessment... & Proprietary Suppl 3 to WCAP-12248 ML20043C5671990-06-0101 June 1990 Discusses Identification of Slave Relays Tested Using Alternative Methodology,Per 900402 Commitment.Encl Tabulation Identifies Test Type,Applicable Procedures & Equipment & Impact of Improper Documentation ML20043E7131990-06-0101 June 1990 Responds to NRC 900517 Notice of Violation & Imposition of Civil Penalty in Amount of $25,000.Corrective Action:Qc Mgt Counseled Level III Inspector & QC Supervisor on Importance of Good Communications W/Receipt Inspectors ML20043C4501990-05-31031 May 1990 Advises That Util Revised FSAR Section 15.1.2 & Question/ Response 32.108,per 10CFR50.59 ML20043B5471990-05-25025 May 1990 Provides Status of Facility Design & Const Activities,Per Request.Detailed Design Work Will Resume in June 1990.Const Activities Expected to Increase Signficantly by Jan 1991 ML20043B5481990-05-23023 May 1990 Provides Clarification of 890710 Commitment Re Power Ascension Program.Cooldown Portion of Remote Shutdown Test Performed During Preoperational Testing,Per FSAR & Reg Guide 1.68.2 ML20043D1711990-05-21021 May 1990 Forwards Public Version of Revised Emergency Plan Procedures,Including Rev 8 to EPP-109,Rev 7 to EPP-112,Rev 4 to EPP-116 & Rev 6 to EPP-121.W/DH Grimsley 900604 Release Memo TXX-9018, Advises of Completion of Implementation of Requirements of Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety- Related Equipment1990-05-21021 May 1990 Advises of Completion of Implementation of Requirements of Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety- Related Equipment ML20043B0981990-05-15015 May 1990 Forwards Radial Peaking Factor Limit Rept for Cycle 1, Containing F(Xy) Limits for All Core Planes Containing Bank D Control Rods & All Unrodded Core Planes ML20042F2851990-05-0303 May 1990 Supplemental Response to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. ML20042F3861990-05-0303 May 1990 Responds to NRC 900410 Ltr Re Violations Noted in Insp Repts 50-445/90-10 & 50-446/90-10 on 900206-07 & 0226-0302. Corrective Action:Memo Issued Emphasizing That Discrepancies Should Be Brought to Attention of Site Organizations ML20042F3021990-05-0202 May 1990 Responds to NRC 900402 Ltr Re Violations Noted in Insp Repts 50-445/89-23 & 50-446/89-23.Util Does Not Believe That Circumstances Described in 900402 Ltr Constitutes Violation of 10CFR50.9(a) ML20042F3051990-05-0202 May 1990 Provides Revised Response to Generic Ltr 88-17 Re Loss of DHR ML20042E4581990-04-12012 April 1990 Responds to Inconsistencies in Terminology & Labelling Identified During NRC 890118 & 19 Audit of Facility Dcrdr. Util Believes Control Room Inventory Requirement of Suppl 1 to NUREG-0737,satisfied ML20042E0701990-04-10010 April 1990 Discusses 900305 Meeting W/Nrc in Rockville,Md Re Offsite Power Availability for Automatic Switch Co Solenoids for MSIV in Event of Nonmechanistic Main Steam Line Crack in Superpipe Region ML20012F5011990-04-0303 April 1990 Forwards Corrections to 891016 Response to Emergency Diesel Generator Engine Requirements.Lengths of Two Pairs of Bolts Above Crankpin Shall Be Measured Ultrasonically Before Detensioning & Disassembly of Bolts ML20012F3221990-04-0202 April 1990 Discusses ESF Sys Slave Relay Alternate Test Methodology. Implementation Schedule for Design Mods to Relay Will Be Submitted by 900601 ML20042D8081990-03-29029 March 1990 Forwards Proposed Change to FSAR Section 13.4 Re Station Operations Review Committee.Similar Change Submitted in 900328 Ltr for Chapter 6 of Facility Tech Specs ML20012F0411990-03-28028 March 1990 Forwards marked-up Pages of Facility Draft Tech Specs & Bases (NUREG-1381) Provided W/Low Power OL ML20012E6051990-03-27027 March 1990 Forwards Endorsements 1-4 to Maelu Certificate M-90, Endorsements 1-9 to Maelu Policy MF-131,Endorsements 29-33 to Nelia Policy NF-274 & Endorsements 1-3 to Nelia Certificate N-90 ML20012E6531990-03-27027 March 1990 Provides Final Response to Reporting Requirement 2 of NRC Bulletin 88-008, Thermal Stresses in Piping Connected to RCS, for Unit.Nde Requirements of Action 2 Not Considered Applicable to Unit ML20012E1911990-03-23023 March 1990 Forwards Comanche Peak Steam Electric Station Unit 1 Cycle 1 Startup Physics Tests Control Rod Worth Predictions Utilizing TU Electric Control Rod Swap Methodology. ML20012E1581990-03-23023 March 1990 Clarifies 880624 Response to NRC Generic Ltr 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants. ML20012D0201990-03-19019 March 1990 Advises That Allegations Provided to NRC by Former Util Employee Unsubstantiated,Based on Investigation by Util Safeteam Organization ML20012E2181990-03-19019 March 1990 Responds to Generic Ltr 89-19 Re USI A-47, Safety Implication of Control Sys in LWR Nuclear Power Plants. Util Determined That Loss of safety-related Inverters 1 or 2 Would Involve Coincidental Opening of Main Feedwater Valves 1990-09-04
[Table view] |
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EE 2 Log # TXX-89565 File # 10010 905.4 Ref. # 10CFR50.55a(g) tilELECTRIC ;
August 21, 1989 Executive Vice President
- g U. S. Nuclear Regulatory Commission
.; Attn:' Document Control Desk Washington, D. C. 20555
SUBJECT:
COMANCFE PEAK STEAM ELECTRIC STATION (CPSES)
-DOCKET NO. 50-445'
~ UNIT 1, INSERVICE TESTING PROGRAM PLAN,
" INSERVICE TESTING OF THE PUMPS AND VALVES" REF: " Request for Additional Information Pertaining to the Comanche Peak'
- Steam Electric Station Unit 1 Inservice Testing Program," from C. I.
. Grimes to W. J. Cahill, Jr.,- dated May 31, 1989 Gentlemen:
In accordance with the-requirements of 10CFR50.55a(g), enclosed are two (2)1.
copies of the CPSES, Unit 1. Inservice Testing (IST) Program Plan, Revision 3.
A copy of the IST Program Plan has also been sent to the Region IV office, the NRC Rt:sident Inspector, the Texas Department of Labor and Standards,' and the Hartford Steam Boiler.
.This Unitol, IST Program Plan, Revision 3, supersedes Revision 2 in its entirety. -Please destroy and discard. previous revisions or drafts currently in your possession. . Revision 3 provides clarifications and' revisions in.- ,
response to the.NRC Staff request for additional information referenced' above. i This revision also' reflects plant changes occurring since the last submittal, various editorial changes, valve additions and deletions, and new or revised relief requests.- Due to the extent of these changes, TU Electric decided to publish Revision 3 of the plan without revision bars. However, in order to q aid.the NRC in-performing its review, revision bars have been added in the _j right-hand margin of the enclosed copies. 1 J
The Unit 1. IST Program Plan, Revision 3 is complete with the exceptions of j any additional relief requests discovered during the performance of the j testing activities.
1 1
MS2Ess BE$yf /Wt1 A 1 I \
400 North Olive Street LB 81 Dallas, Texas 73201
4
<y I
- TXX-89565
- August 21, 1989 Page 2 of.2 TU; Electric has completed she review and evaluation of the Open Items which
- resulted from the meeting held among the NRC, CASE, and TU Electric on July 19'and 20, 1989. A. summary of the meeting discussion and the responses to these Open Items, with applicable. comments / justification to support conclusions, are oelineated in the attachment. The attachment format includes the original NRC question and comment, a summary of the discussion as provided by the NRC during the working meeting, and TV Electric's Response provided to close the issue.
Sincerely, E .
t William J. Cahill, Jr.
DAR/vid
Attachment:
Responses to the Open Items
Enclosure:
CPSES Unit 1 Inservice Testing Program Plan, Revision 3 c Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3)
Texas Department of Labor and Standards Boiler Division E.' O. Thompson State Office Building-P. 0. Box 12157, Capitol Station l Austin, Texas 78701 Attn. George Bynog Hartford Steam Boiler 15415 Katy Freeway Houston, Texas 77094 Attn. Tom Barbara I
r L___n___________________________________ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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Attachn nt to TXX-89565-August 21. 1989
'Page l'of 8' TU ELEi;TRIC'S RESPONSE.TO THE
< REQUEST FOR ADllITIONAL INFORMATION PERTAINING TO THE COMANCHE PEAK STEAM ELECTRIC STATION-UNIT 1 INSERVICE TESTING PROGRAM OPEN ITEMS FOR THE LICENSEE q
- 1. VALVE TESTING PROGRAM A. General Questions and Comments
- 7. The NRC staff positions regarding limiting values of_ full-stroke times for power operated valves are explained in detail in Generic Letter 89-04. " Guidance on Developing Acceptable Inservice Testing Programs."
Are the Comanche Peak Methods;for the determination of limiting values of full-stroke time in compliance with these NRC staff positions?
Discussion:
The CPSES IST ' Pl an utilizes reference . values in lieu of stroke time trending- as described in Relief Request V-2. ' Deviations from
, the fixed reference values are evaluated to determine a valve's acceptability for continued operation. The evaluation criteria will be contained in the applicable procedures and the results will be documented with the data.
CPSES utilizes reference values of full-stroke time, alert values based on these reference values, and limiting values of full-stroke time. However, the limiting values of full-stroke time are currently based on system operability requirements.
The Code requires the owner to specify the limiting value of full-stroke time for each power operated valve. The NRC staff position is that the limiting value of full-stroke time should be based on the valve reference or' average stroke time of a valve when it is known to be in good condition and operating properly. The limiting value should be a reasonable deviation from this reference stroke time based on the valve size, valve type, and actuator type. The deviation should not be so restrictive that it results in ~ a valve being declared inoperable due to reasonable stroke time variations. When the Technical Specification or safety analysis limit for a valve is less than the value l
established using the above guidelines, the Technical
- Specification or safety analysis limit should be used as the l limiting value of full-stroke time. When the Technical L
Specification or safety analysis limit for a valve is greater than l
the value established using the above guidelines, the limiting value of full-stroke time should be based on the above guidelines l instead of the Technical Specification or safety analysis limit.
This is an OPEN ITEM for the licensee.
LE_________________.____._______________ _ _ _ __ ___ _ _ _ _ _ _ _ _
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'Attachrnt to:TX'X-89565 August 21, 1989-Page.2 of 8 TU ELECTRIC'S Response:
-The stroke times have been removed from the valve tables in the CPSES IST Plan. The TV Electric procedure for inservice. pump and-valve testing will be revised to add a table that lists' valves-to be exercised, the Technical Specification' stroke time limit ' for each valve listed, and the limiting value of full stroke ~ time which will be determined in accordance with Generic Letter 89-04 (i.e., based on the valve reference value).
D. Main Steam. Reheat. and Steam Dump System
- 3. How is a full-stroke to the open position verified quarterly for valves 1-MS-142 and -143? What testing is performed. to verify the closure capability of these valves during cold shutdowns?
Discussion:
The full-stroke of valves 1-MS-142 and 1-MS-143 to' the open position during quarterly testing performed by the passage of main steam through one check valve to operate the turbine driven auxiliary feedwater pump.
One check valve will be disassembled during refueling outages in lieu of a cold shutdown closure test. A suitable relief request '
will be provided in the CPSES IST Plan to address this activity.
The licensee will evaluate whether the steam flow through this valve is equal to or greater than the accident- required steam flow.
The NRC staff position is that valve disassembly and inspection can be used as a positive means of determining that the valve's disk will full-stroke exercise open or of verifying closure capability, as permitted by IWV-3522. However, to grant relief which allows this testing to be performed at a refueling outage frequency, the licensee must demonstrate that it is impractical to perform the Code required testing quarterly, and at a cold shutdown frequency. In order to grant relief which allows this testing to be done on a sampling basis, the licensee must also demonstrate that all other means of testing are impractical, and that it is burdensome to disassemble all valves each refueling' outage.
TV ELECTRIC'S Response:
These valves have been added to the CPSES IST Plan to be full-stroke tested to the open position quarterly by passing steam flow, which is equal to or greater than the accident required flow, through the valve and tested to closure during cold shutdown as defined in the CPSES IST Plan. .
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Attachtent to TXX-89565'
-~
LAugust- 21, 1989 Page'3 of 8 E. Auxiliary Feedwater System
.3. Do the following check valves perform safety functions in the closed position'to prevent back flow of high temperature feedwater and/or to prevent diversion of flow if an auxiliary feedwater pump is not operating?
1-AF-075 1-AF-078 1-AF-083 1-AF-086 1-AF-093 1-AF-098 1-AF-101 1-AF-106 Discussion:
In addition to providing an auxiliary feedwater flow path to the steam -generators, these check valves also perform a safety function in the closed position. Therefore, a requirement to test these valves in a manner that proves the disk travels to the seat promptly on the cessations or reversal of flow will be added to the CPSES IST Plan. Verification' that 'the valve is in the closed position will be by positive means (such as pressure, temperature, or radiography) on a ccid shutdown frequency. No additional testing needs to be performed unless there is._ an indication that the closure capability of a valve is questionable, than the valve-must be declared inoperable and either be disassembled and visually- inspected, or be repaired, or replaced prior to . being returned to service.
The licensee should determine the maximum back leakage through these valves that the auxiliary feedwater system could tolerate.
This maximum quantity of back leakage should be incorporated into back leakage testing on these valves. Further, the licensee should incorporate a surveillance monitoring system. This is an OPEN ITEM for the licensee' .
TU ELECTRIC'S Response:
It is the owner's responsibility to define the ASME Section XI valve category for each valve to be tested. Check valves, for which seat leakage is not limited to a specific maximum amount by Technical Specifications or the FSAR, are categorized as "C" only in the CPSES IST Plan. Verification of closure will be by positive means.
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. Attachnnt'to TXX-89565 August 21,.1989 Page.4 of 8..
F. Component Cooling t'cter. System
- 1. Do vaives 1-LV.-4500,.-4501, and -4501-1 perform a safety function? 'Do these valves have a required fail-safe' position?
Discussion:
The safety function of'these valves is to provide.make up water to the. component cooling water surge. tank. They are located within seismic category I. classified piping lines. ; The design basis allows operator -action to manually open these valves ~ if they are-unable to open automatically. Therefore, they are not subject to ASME Section XI inservice testing. These valves will receive non-ASME Section - XI fail safe position and exercise surveillance testing.
If a valve- performs an ' active safety function then. Code requirements do apply. The. licensee.will evaluate' whether these valves perform a safety function. This is an OPEN ITEM for the licensee.
.TU ELECTRIC *S Response:
These - valves perform a safety function and testing. requirements have been added to the CPSES IST Plan.
- 2. What is the safety function of the following valves?
PC/-H116A PCV-H116B XPV-3583 XPV-3584 XPV-3585 XPV-3586 Discussion:
These valves function as control valves for air conditioning units as described in the notes section of the CPSES IST Plan. The licensee will verify that valves PCV-H116A and PCV-H116B do not have a required fail-safe position. The licensee will note the results of this review in the IST plan.
TU ELECTRIC'S Response:
Valves PCV-H116A and PCV-H116B do have a required fail-safe position and fail-safe test requirements have been added to the CPSES IST Plan.
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- Attachrent'to TXX-89565 August _21, 1989-Page 5,of 8
'M. Containment Soray System 2 .- Review the safety function oof check valves ICT-047 -048, -063,_and
-064- to determine:if they should be included in the IST program and tested to_the Code requirements.-
Discussion:
l Check - valves . l 1CT-047, -048, -063, and -064 ' provide' mini-flow protection for the containment spray pumps. The piping in the mini-flow line was recently ' upgraded to Class 2 by DMRC No.
'87-1-088. These valves will be added to the CPSES IST Plan 'and tested to'the Code requirements.
The licensee will evaluate methods to verify a full-stroke' test of these valves (there is no flow instrument in the mini-flow line).
TU Electric's Response:
Portable, ultrasonic flow meters or system instrumentation will be used during testing to verify a full-stroke test for these valves.
O. Safety In.iection System-
- 7. How are valves 1-8818A, -8818B, -8818C, and -8818D verified to individually. full-stroke open during cold shutdowns? Also, provide a -
technical justification for not part-stroke exercising these valves quarterly.
Discussion:
Compliance with Reactor Coolant System technical specifications for' pressure isolation valves requires a leak test each time these valves are disturbed. Therefore, deferral of any testing to cold shutdown conditions was specified to collect meaningful data and to verify operability when the valves could be leak tested using the SI system test header.
The full stroke of valves 1-8818A, B, C. and D can be verified by monitoring flow and pump operating parameters to baseline condition. The failure of one check valve in each parallel branch to open would alter system resistance character # ctics and result in a change in pump operational parameters.
The NRC staff position is that a full-stroke of each valve must be individually verified. The licensee will evaluate the methods of individually verifying the full-stroke of each valve. This is an OPEN-ITEM for the licensee.
TU Electric's Response:
1 These valves have been added to the CPSES IST Plan to be partial-stroke tested during cold shutdowns (as defined in CPSES IST Plan)
! and full-stroke tested during refueling outages utilizing test equipment to quantify flow in the parallel branch injection lines, b
m '"
Attach = nt to'TXX-89565 August 21, 1989 Page.6 of 8 P. Chemical and Volume Control System
- 1. Provide a detailed technical justification for not testing valves 1-8153 and -8154 quarterly to the Code requirements.
Discussion:
The Chemical and Volume Control System valves 1-8153 and -8154 are
- not required to be tested to ASME Section XI requirements. These normally closed, fail closed valves- constitute the pressure boundary between the Class 1 RCS and Class 2 excess letdown line, per ANSI N18.2a-1975. These valves - are ' not high/ low pressure system _ interfaces and are not listed as RCS pressure isolation valves in Technical Specification Table 3.4-1, Note that the penetration valves 1-8112 and 1-8100 are tested to ASME Section XI requirements.
The licensee will. either identify these valves as non-safety-related in the IST program or will delete them from the program.
TV ELECTRIC'S Response.
These valves' have been added to the CPSES IST Plan to be full-stroke tested quarterly.
- 2. Table'16 of the Comanche Peak IST program identifies the following check valves as pressure boundary isolation valves. Pressure boundary isolation valves have a safety function in the closed position.
Valves which are normally open, or may be required to open, during plant operation which have a safety function in the closed position are not passive valves. Provide a detailed technical justification for not testing these valves to the Code ~ requirements.
1-8378A 1-8378B 1-8378C 1-8378D 1-CS-8350A 1-CS-8350B 1-CS-8350C 1-CS-8350D 1-CS-8367A 1-CS-8367B 1-CS-8367C 1-CS-8367D Discussion:
The response for these valves is similar to the response provided in 1.0.1 above [the response to Question 1 of Item 1.0 in the ,
reference, " Chemical and Volume Control System"]. These valves i are at the Class 1 RCS to Class 2 CVCS interface per ANSI N18.2a- 1 1975. and unlike the valves listed in Technical Specification Table 3.4-1.. are not in high/ low pressure system interfaces.
The licensee will either identify these valves as non-safety-related in the IST program or will delete them from the program.
TU ELECTRIC'S Response:
l L These check valves have been added to the CPSES IST Plan to be tested in accordance with relief request nos. 16.6 and 16.7.
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X' 'Attachrnt'.to TXX-89565-August 21,l1989
, .;Page 7 of 8
- 3; . Evaluate whether check valve 1-8381 has a safety function in the open -
l position and should be exercised to the~open position. Also, Table 16 1
should indicate that this valve'is~ exercised to the closed position at-a refueling outage frequency.
Discussion:
.. , The primary function of 1-8381 'is to p'tvide containmentLisolation for the normal charging header. As such, the' valve is Appendix.J
'
- tested. The auxiliary spray - valve 1-8145 and check valve ~ 1-CS-
'8377 were added to the CPSES . IST Plan. . therefore, auxiliary spray does require' the operation of '1-8381. This valve will be exercised to the open position.
The licensee will verify that . normal charging flow will full--
stroke exercise this valve.
TV ELECTRIC *S Response:
Full-stroke exercising, in. accordance with Generic Letter 89-04..
of Valve 1-8381 will be accoinplished by normal charging flow.
Q. Safety Chilled Water System
- 1. Whatisthe~safetyfunctionofvalves1-CH-300,1-CH-301,'andl 1-HV-8720..
Discussion:
The safety function of these valves is to provide make up water to the' component cooling water surge tank. They are located within seismic ~ category I classified piping lines. The design basis allows operator action to manually open these valves if they are unable to open automatically. Therefore, they are not subject to ASME Section XI inservice testing. These valves will receive non-ASME Section XI fail safe position and exercise surveillance testing.
Per NRC staff position, if a valve performs an active safety function then Code requirements do apply. The licensee will.
evaluate whether these valves perform a safety function. This is an OPEN ITEM for the licensee.
TV ELECTRIC'S Response:
These valves perform a safety function and testing requirements have been added to the CPSES IST Plan.
,d* 'Attachwnt to.TXX-89565 m : August;21, 1989 Page 8 of 8 S. SDent Fuel Pool Coolino System
- 1. Provide: P&ID - no. 2323-M1-0235 - for our review. Do . valves XSF-003,
-004 -160, . and -180 . perform . a ' safety function? If so, provide a:
technical ' justification for not testing .these valves in . accordcnce with the Code requirements.
Discussion:
1 The NRC staff position is that the Spent Fuel Pool Cooling System pumps and valves should'be included in the IST program, unisss the-licensee . has. safety grade makeup- _ and . building L
ventilation / filtration systems. The licensee will include this system in their IST program. 'The licensee will evaluate the testing currently performed and the testing required by the.. Code.
Relief' request may be submitted for the Code instrument accuracy requirements TU ELECTRIC *S Response:
The. Spent Fuel Pool Cooling System has been reviewed and a determination has been made that these check valves perform a safety function and have been added to the CPSES IST Plan to be full-stroke tested quarterly, i
- 2. Loss of cooling ' and/or makeap water to the spend fuel pool could result in over heating of spent fuel and the release of fission =
products and radioactive contamination. Therefore, the NRC requires (refer to NUREG-0800,- Section 9.1.3) that safety related cooling be available for the spent fuel pool and that all active pumps and valves in this cooling water supply be included in the IST program' and. be tested to the Code requirements except where specific relief is requested and approved. What safety related cooling is provided to the spent fuel pool? List the components (if any) that will be added to the IST program and identify the testing that will be performed.
Discussion:
The NRC staff position is that the Spent Fuel Pool Cooling System pumps and valves should be included in the IST program, unless the licensee has safety grade makeup and building ventilation / filtration system. The licensee will include this system in their IST program. The licensee will evaluate the testing currently performed and the testing required by the Code.
Relief request may be submitted for the Code instrument accuracy requi rements .
TU Electric's Response:
The spent fuel pool cooling pumps (active valves as described in the response to Question 1 of Item 1.S above) have been added to the CPSES IST Plan to be tested in accordance with the code.
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