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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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=M Loa # TXX-6769 W
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= = 915.8 h p\ q H# ELECTRIC . Ref # 10CFR50.62 (c)(1) f'\ <
l-k H;Iliam G. Counsil
.Esecutive Vice President t
-l U. S. Nuclear Regulatory Commission q'y
' Attn: Document Control Desk Washingten, DC 20555 s r t' ,
SUBJECT:
COMANCHEsPEAK STEAM ELECTRIC STATION (CPSES) I DOCKET N05. 50-445 AND 50-445 '7 IMPLEMENTATION OF GENERIC LETTER 85-06 7;<
ANTICIPATED TRANSIENTS WITHOUT SCRAM (ATWS)
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REFERENCE:
W. G. Counsil letter TXX-6416 to NRC dated "L kS I fpril29,1987
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Gentlemen: c ,
,. 4 On April 16, 1985, the NRC staff issued Generic Letter 85-06 to address <
quality as'surance requirements for non-safety ATWS equipment. Specifically j.ir, the letter requires Westinghouse near term operating licensees to submit an jl implementat6cn schedyle for the ATWS Mitigating System Actuation Circuitry (AMSAC), which will meet the requirements of 10CFR50.62 paragraph (c)(1).
Attached is TV Electric $ response which addresses the plant specific requirements, as designated in WCAP,-10358, AMSAC Generic Design Package, which was approved by thq NRC with the Safety Evaluation and WCAP-10858P-A Rev.11/
which was submitted to the NRC August 3, 1987 to provide further consideration of the AMSAC arming setpoint, C-20. CPSES utilizes the steam generator low low water level for its plant specific design logic. As stated in the reference letter, AMSAC is scheduled to be implemented at CPSES by March 1988. !
Very truly yours, -
$$ Y 8710150110 871009 W. G. Counsil' PDR ADOCK 050C0443 A o VIP:tgj [' FDR
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Attachment c- Mr. R. D. Martin, Reaion IV l 4
Residentinspediors(3) g
, I 400 North Olise Street LB 81 Dallas, Texas 75201
Wk Attachment to TXX-6769
/'~i' . October 9, 1987 Page 1 of 13 ,
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cm 3 ANSAC SAFETY EVALUATION REPORT RESPONSE FOR COMANCHE PEAK STEAM ELECTRIC STATION TVElectrichasselectedhdwillimplementanAMSACactuationlogicwhich detects a loss of heatsink by monitoring the water level in each of the steam
. generators. This actuation logic incorporates an automatic arming and block circuitry based upon turbine load by monitoring the first-stage turbine i
impulse chamber pressure. This signal, referred to as the C-20 signal, blocks l AMSAC actuation at low power levels to prevent spurious trips during plant
( siart-ups. This actuation logic is depicted in Figure 1.
The basis for this design can be found in WCAP-10858, AMSAC Generic Design Package, which was approved by the NRC with the Safety Evaluation and WCAP-10858P-A Rev. 1, which was submitted to the NRC August 3, 1987 to provide further consideration of the AMSAC arming setpoint, C-20. The Comanche Peak design does not deviate from the submitted package and the following is the response to the fourteen (14) items requested in the SER for the plant specific submittal.
Diversity The basis for diversity of the ATWS mitigation system from the existing reactor trip system is to minimize the potential of common mode failures.
This diversity is required from sensor output to, but not including, the final actuation device, e.g., existing circuit breakers may be used for the auxiliary feedwater initiation. For Comanche Peak, the existing transmitters, transmitter )ower supplies, and new isolators associated with the turbine impulse cham 3er pressure and narrow range steam generator level loops in the 7300 process protection system will provide the input for AMSAC. The Westinghouse AMSAC design is a microprocessor-based system with the capability to incorporate three different actuation logic schemes: Comanche Peak will employ actuation based on low steam generator water level. The reactor trip system utilize an analog-based process protection system and discrete component logic system. Therefore, Comanche Peak fulfills the requirement of diversity through the types of technology (analog vs. dig;tal) and hardware utilized. Where similar components are utilized for the same function in both AMSAC and the reactor trip system, the components used in AMSAC are provided from a different manufacturer. For example, relays are utilized in both systems for interfacing with the final actuation circuits. At Comanche Peak, Potter-Brumfield and SR relays are utilized within the reactor trip system while Struthers-Dunn relays are used within AMSAC.
Logic Power Supplies According to the rule, the AMSAC logic power supply is not required to be safety related. However, the logic power supply should be from an instrument s
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Attachment to TXX4769 s ! >
. October 9, 1987 Page 2 of 13 '
power supply that is independent from the reactor protection system power supplies. At Comanche Peak, AMSAC logic cabinets will be powered from a non-class IE uninterruptible power supply (UPS) source. This will ensure availability of power during lost of off-site power. ;
Safety-Related Interface d
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Thd hM40 rin$ts for measuring turbine impulse charber spessure and narrow rangs steam generator water level are derived from exding transmitters.
Connections ta those channels are made downstream of class IE isolation devices which areJacated within the process protection cabinets. These isolation devices ensure that the existing protection system continues to meet >
all applicable safety criteria by providing isolation as demonstrated in Appendix A of this submittal. 7M o Tput isolation device is the interface ',
that separates the ATWS equ yment from the safety related equipment. To show that the implementation of the, interface is such that the existing protection. . 2 system continues to meet all' applicable safety criteria, the isolation device l will be a qualified device ccnsistent' with the requirements of Appendix A of 3 the NRC SER ant ~can be foted in Appendix A of this document. '
l a ;l Quality Assurance <
, i Generic letter (GI,) 85 06 provides explicit QA guidance for non-cafety related !
ATWS equipment as required by 10CFR50.62. The GL specifically states that the i QA program fonthuun-safety related ATWS equipment does not need to meet the i requirements of 10CFR50 Appendh B nor would compTiance be judged in terms of
, the Appendix. Detaile( CA guidance will be in accordance with the enclosure to the GL. For Manufactiwing, the hostinghouse program exceeds the above requirement. Quality Assuruce, for plant modifications involving, design, procurement & installation fWAMSAC equipert will be in accordance with existing plant pf f:edures. For testing tnd maintenance, procedures will be developed based on tha Westinghouse recommendations /' technical manua's' } "for the equipment as required.
) ,
Maintenance Bypasses liaintenance at power is' accomplished through a permanently in.;talled bypass switch. This complies with the NRC SER because this method does not involve lifting leads, pulling fuses, tripping breakers or physically blocking relays.
Rotating of the AMSAC bypass switch to the " bypass" position inhibits operation of the system's outpot raleys which operate the final actuation ,
devices. Status outputs to the plant computer and main control board. ,
indicating that a general warning condition (AMSAC trouble) exists with AM5AC, areL initiated when the bypass switch is placed in 'the " bypass" position.
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Attachment to TXX-6769
. October 9, 1987 Page 3 of 13 Operating Bypasses Letter 00-87-10 dated February 26, 1987 has been submitted to the NRC by the Westinghouse Owner's Group (WOG) to provide the basis for the C-20 setpoint.
The C-20 permissive signal uses the existing turbine impulse chamber pressure sensors. Short term protection against high reactor coolant system pressures is not required until 70% of nominal power. However, in order to minimize the amount of reactor coolant system voiding during an ATWS, AMSAC will operate at and above 407 of nominal power. Furthermore, the potential exists for spurious AMSAC actuations during start-up at the lower power levels. To assure these requirements are met, AMSAC will be automatically blocked by the C-20 permissive at turbine loads less than 40%.
The operating bypass status of the AMSAC system will be indicated (status light) on ,the main control board at the permissive and control interlock panel and will also be an input to the plant computer. The indication of maintenance bypass mentioned earlier and operating bypass will be consistent with the existing control room design philosophy and human factors engineering considerations, For guidance on diversity and independence for the process equipment and logic power supplies, see those specific sections.
Means for Bypass Bypassing of AMSAC is accomplished with a permanently installed, human factored bypass switch. It does not involve lifting leads, pulling fuses, triNNg breakers or physically blocking relays.
Manual Initiation At Comanche Peak, manual AMSAC actuation is not provided since the turbine can be tripped manually in the Control Room or locally at the turbine. Manual tripping is accomplished by depressing the " turbine trip-push button" or by
" pulling-to-lock" the control switch for the control fluid pumps. The push button and control switch are located at the main control board. The turbine can be manually tripped via a local trip valve located at the hydraulic control rack.
The auxiliary feedwater pumps can be manually started in the control room or at the hot shutdown panel. Manual starting is accomplished by positioning the individual auxiliary feedwater control switches to the " START" position.
Manually tripping the turbine and starting the auxiliary feedwater pumps are accomplished in accordance with existing plant operation procedures.
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Attachment to TXX-6769
. October 9, 1987 )
Page 4 of 13 i Electrical Independence I
l Electrical independence from the existing reactor trip system is required from the sensor output to, but not including, the final actuation device. This is a separate safety related circuit from the non-safety related circuits. The Conianche Peak AMSAC fulfills this requirement. For the turbine impulse chamber pressure input, TV Electric has elected to use the existing pressure a transmitters, loop power supplies, and new isolation devices within the 7300 J system process protection cabinets. In a like manner, existing narrow range level transmitters, loop power supplies and new isolation devices within the )'
process protection cabinets will be utilized for measuring level in each steam generator and therefore, will also be electrically independent from the reactor trip system. Moreover, the non-class 1E logic circuitry and outputs of AMSAC are isolated from the class 1E turbine trip circuits and the class 1E auxiliary feedwater start circuits. Information pertaining to the isolation devices utilized can be found in Appendix A of this document.
Physical Separation The ATWS equipment must be physically separated from the existing protection system hardware. This requires that the ATWS cable routing be independent of protection system cable routing and the location of the ATWS equipment cabinets, such that there is no interaction with the protection set cabinets.
The basis of this requirement is Regulatory Guide 1.75, Revision 2, which endorses and augments IEEE 384-1974 requirements and criteria applicable to class 1E instrumentation cabinets. The AMSAC actuation outputs to the redundant turbine trip and auxiliary feedwater pump circuits are separated by providing separate relay panels within the AMSAC cabinet. Additionally, the isolation fault tests mentioned in Appendix A will demonstrate that credible faults will not disable channels associated with other protection sets. All non-class IE AMSAC inputs and status outputs will be routed to a separate ,
logic cabinet and therefore, will be separate from the class 1E actuation '
circuits. Figure 2 depicts the system block diagram along with the cable I separation groups.
l Equipment Qualification The SER requires that only the isolation devices comply with environmental qualification (10CFR50.49) and with scismic qualification, which is discussed in Appendix A. The environmental qualification of the remaining portion of the hardware will be addressed here. The ATWS mitigation system is not required to be safety related and therefore, is not required to meet IEEE-279-1971, nor be environmentally qualified. The portion of the ATWS mitigation '
equipment located outside containment in a mild environment area follows the same design standards as non-class 1E control-grade equipment. For this modification, there is no additional equipment inside containment; the existing equipment inside containment is qualified.
Attachment to TXX-6769 J
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October 9, 1987 Page 5 of 13 Testability at Power The non-safety related ATWS circuitry is testable with the plant on-line.
Testing of the AMSAC outputs to the final actuation devices may be performed with the plant shutdown.
The AMSAC systems for Comanche Peak provide for periodic testing through a series of overlapping tests. These tests are performed with the AMSAC outputs bypassed as described in the " Maintenance Bypasses" section.
Once the system bypass is established, a series of overlapping tests are performed to verify analog channel accuracy, setpoint (bi-stable trip) accuracy, coincidence logic operation including operation and accuracy of all timers, and continuity through the cucput relay coils. Switches will be i provided for each output relay to allow testing of AMSAC outputs to the final actuation devices with the plant shutdown. Figure 3 is a simplified block diagram reflecting the test overlaps for the periodic on-line tests. A summary of each of the overlapping tests is provided below:
Analoa Inout Channel Testing - The field input to each analog input channel .is replaced with a variable test reference which is used to confirm accuracy of the channel gain and offset. The test referer.ce is then ramped up and down throughout a portion of the channel range to verify accuracy of the channel setpoint and associated deadband. This test confirms operation of the input channel signal conditioning circuitry, analog-to-digital converters, and the processor.
Processor Loaic Testina - The second sequence of testing verifies that each Actuation Logic Processor performs the preoer coincidence logic, including timing functions, and generates the proper outputs. In this test, the field input to each input channel for the processor under test is replaced with test references. The test references simulate the channel values as either above or below the setpoint to verify combinations of coincidence logic to perform the generation of the proper processor outputs to the majority voting modules. This test confirms operation of the input channel signal conditioning circuitry, analog-to-digital converters, processor operation and output circuitry to the majority voters.
Ma.iority Voter and Output Relav Tests - Each majority voting module and associated output relays are tested to verify operation of the majority vote (2 out of 3) and that continuity exists for each of the output relay coils. Integrity of the relay coils along with associated wiring is verified by exercising the voting logic.
Attachment to TXX-6769
. October 9, 1987 Page 6 of 13 Completion of Mitigative Action The AMSAC output contacts automatically reset through processor logic and can not be manually reset'at the AMSAC cabinet. These contacts are connected in parallel or series with the existing actuation contacts in the plant control circuits. These control circuits have seal in/ latching and manual reset features.
AMSAC output contacts, once actuated, will complete the mitigative action as discussed below:
Turbine Trip - The AMSAC output contact on momentary closure energizes the turbine trip solenoid valve. This releases valve hydraulic fluid pressure which results in closing of the main stop valves. Return to normal operation is accomplished by the operator. !
Motor Driven Aux. Feedwater Pumps - The AMSAC output contact on momentary l Bosure energizes the DC closliig coil to close the motor driven auxiliary feedwater pum) breaker. The breaker remains closed until a trip signal occurs. The areaker closure starts the auxiliary feedwater pump. Return to normal operation is accomplished by the operator.
Turbine Driven de-energizes theAux. Feedwater solenoid Pump'the isolation valve.-On
~to open The AMSAC opening output contac of the valve, the valve limit switch contact in the control circuit opens to keep the solenoid de-energized. Return to normal operation is accomplished by the operator.
Steam Generator Blowdown and Sampling Isolation Valves - The AMSAC output contact, on opening, de-energizes the solenoid to close the valve. On closing of the valve, the valve limit switch contact in the control circuit opens to keep the solenoid de-energized. Operator action is required for opening the valve.
Technical Specifications The WOG is on record (cf. 0G-171, dated February 10,1986) that Technical Specifications for AMSAC are unnecessary. As of May 30, 1987, the NRC has not responded to the WOG letter.
TV Electric feels that Technical Specifications for AMSAC do not enhance the overall safety of the nuclear plant and constitute a backfit. TV Electric also believes that normal nuclear administrative controls are sufficient to control AMSAC.
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LA'tachment'to t TXX-6769-
-. " October 9, 1987 Page 7 of-13 APPENDIX A - AMSAC ISOLATION DEVICE
- Electrical . independence. of AMSAC- from the existing Reactor Protection System
-(RPS) is provided .through several means at Comanche Peak. A block diagram
-. showing the rela _tionship of AMSAC to the existing RPS is provided in Figure 4 which details the AMSAC/RPS connections and points of isolation.
The steam generator narrow range level inputs.to AMSAC will be derived from existing signal loops within the process protection cabinets. These signals are provided from differential pressure transmitters to the process protection
-cabinet'and from the protection cabinet to the AMSAC cabinet. Additional isolator cards will be added in the process protection cabinets to provide isolated . signals to AMSAC.-
'TU Electric has elected to utilize the existing pressure transmitters for 1 measuring turbine load at the first stage. As with the narrow range steam generator level inputs, the isolated signals for turbine load will be provided from the process protection cabinets to the AMSAC cabinet.
Isolation is.provided in the process protection cabinet for the signals used as input for AMSAC. As reported in WCAP-8892A, Westinghouse 7300 Series Process: Control System' Noise. Tests, these isolation devices which are powered 1
.from a class'1E source, have been tested to demonstrate that the device is acceptable for its application. The purpose of the tests was to determine whether protection circuitry could be disturbed to the extent that protective action would be prevented by the pick-up or presence of credible interference on control wiring in close proximity to protection wiring within the process control racks. Isolation devices are used in the Process Control System 7300 Series equipment to electrically isolate the protection. circuits inside the ;
process control racks from control circuits outside the cabinets. The system !
was subjected to tests that included magnetic noise test, output cable voltage !
faults (maximum credible voltages: 550 VAC, 250 VDC), cross talk, random noise test, etc... The acceptance criteria for these tests were a) the postulated fault should not prevent required protective action, and b) spurious protective action caused by the postulated fault should be acceptable.
As mentioned, the subject of interferences that could negate protective ;
actions was covered in various tests carried out for the WCAP (Westinghouse 7300 Series Process Control System Noise Tests). This report includes a l, series of tests that were performed before any faults or circuitry abnormalities were applied. These tests demonstrated that a credible disturbance in the control wiring would not degrade protective action or be
)
reflected back into the protection wiring. Any of these interferences (i.e., 1 noise, crosstalk. etc.) that would be generated by AMSAC falls under the same category as those tested in the test report. Since AMSAC is separate from the RPS.and the cable is not routed in an area that exceeds the 550 VAC 250 VDC test limits, any interference from AMSAC would not affect the RPS.
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. Attachment to TXX-6769 October 9, 1987 Page 8 of 13 Under all test conditions the protection circuitry operated as intended. The test showed conclusively that electrical interference imposed onto the isolator output wiring (control wiring) does not affect proper operation of the perturbed channel nor any adjacent channels. The recordings verify that the interference imposed onto the control wiring was not induced into the protection wiring. The magnitude of the electrical interference introduced into the system and the stringent test procedures far exceeded any conditions that would be present in actual plant operations. l Relays are provided at the output of AMSAC for isolating the non-class 1E l AMSAC circuits from the class 1E final actuator circuits. At Comanche Peak, the AMSAC outputs are provided from separate relay panels within the AMSAC cabinet. Separation of the Train A and B circuits within the AMSAC cabinet is achieved through a combination of metal barriers, conduit and distance. These relays will be tested with the maximum credible faults applied to the relay coil in the transverse mode. Tests will be performed with the relay coil operating contact in both the open and closed position. Figure 5 depicts the simplified diagram of this output isolation circuit, and point of application for the maximum credible faults. Details of the actual tests, fault levels and their origin, test data, and the pass / fail acceptance criteria will be submitted upon completion of the test.
For Comanche Peak, the isolation devices comply with the environmental qualifications (10CFR50.49) and with the seismic qualifications which were the basis for plant licensing.
The class '1E loads operated by the isolation relay contacts are powered from a class 1E source. The plant specific details of the wiring configuration can be found on the TU Electric elementary drawing.
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"80 N M FRoM UNINTERRUPTIBLE POWER SUPPLY I 1 I l I DISTRi BUTION . PANEL..
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- CN.1&2 TURBINE PRESSURE LOW - MMC BLOCKED J TURBINE < 40% POWER I C-20 ( STATUS L(GHT) j 1
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- CLDSCS STW., BLOWDOWN SWPLIS UNES FIGURE 2 : RPS-AMSAC BLOCK DIAGRAM
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Attachnent to TXX-6769 Septembe '25, 1987 l Page'12 of 13 sarm RaAtto TURBINE IMPULSE PRESSURE TRANSMITTERS ,
naD SDGORS i S/G N.R. LEVEL TRANSMITTERS
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