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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] |
Text
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Log # TXX-4382
-. File # 10010 TEXAS UTILITIES GENERATING COMPANY 907.5 MKYWAY TOWER
- 400 NORTH OLIVE MTREET. L.B. M8
f,H ?,EC January 28, 1985 i
Director of Nuclear Reactor Regulation 1 Attention: Mr. B. J. Youngblood, Chief Licensing Branch No.1 ,
Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555 ,
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NOS. 50-445 AND 50-446 ,
RESPONSE TO NRC STAFF INTERIM EVALUATION ON ACCIDENT M)NITORING l l
REF: (1) B. 'J. Youngblood to M. D. Spence letter of November 15, 1984, entitled, "EC Staff Interim Evaluation Report Concerning Comanche Peak Steam Electric Station Emergency Response Capability Conformance with Regulatory Guide 1.97, Rev. 2"
Dear Sir:
Reference' (1) provided an interim evaluation by the NRC staff on the compliance of the Comanche Peak Steam Electric Station (CPSES) design with the guidance-provided in Regulatory Guide 1.97, Rev. 2. The CPSES design has been reconsidered in light of this NRC Staff interim evaluation. In ,
the attached response, additional information has been provided to better !
justify the acceptability of the CPSES design for several of the Accident l Monitoring parameters.
As part of this response, a comitment has been provided to modify the CPSES design with respect to three parameters (SI Accumulator Pressure, i Pressurizer Heater Status, and Containment Atmosphere Temperature). These backfits will be completed prior. to startup for the second operating cycle l for _CPSES Unit 1 or as agreed upon with the NRC staff in a living schedule i for CPSES Unit 1. j l
09 g!A"RB8WJB8Qg k8 g$
I A DIVIMION OF TEXAN UTILITIEN ELECTRIC COnll'ANY I
The additional information and the backfit commitments provided in the o- attached response are intended to provide the input needed by the NRC staff to accept the CPSES Accident Monitoring design. The CPSES FSAR will be updated in an upcoming amendment to reflect these changes.
Respec tfully, u.%
John W. Beck DRW:grr Attachment Distribution: Originaf"pluE40 lcokies)
,_nm.. .-,.--.,,-...-v,
1
. ATTACHMENT TO TXX-4382 TUGC0 RESPONSE TD THE NRC STAFF INTERIM EVALUATION REPORT CONCERNING CPSES CONFORMANCE TO REG. GUIDE 1.97 REY. 2
Reference:
NRR letter of November 15, 1984 A response to the NRC Staff's interim evaluation of the Accident Monitoring
' design for the Comanche Peak Steam Electric Station (reference 1) is provided below. This response is intended to significantly advance the 1 efforts to resolve this issue. The paragraphs below are numbered the same as the' corresponding sections in the interim evaluation to allow for easy
.' identification.
- 1. The NRC Staff evaluation was performed through amendment 45 of the CPSES FSAR. An additional deviation from Reg. Guide 1.97 Rev. 2 was added to the CPSES FSAR by amendment 52. This deviation involves the range used to measure Atmospheric Stability. CPSES uses a range from -50F to +50F while Reg. Guide 1.97 Rev. 2 reconnends a range of -50C to +100C.
This deviation is justified because the CPSES range of -50F to +50F which
-respresents the difference in temperature between the 10 meter and the 60 meter levels on the primary meteorological tower is equivalent to -2.780C to +2.780C for a 50 meter span or -5.560C to +5.560C for'an equivalent 100
- meter span. The -5.560C lower limit is less than the -1.90C limit that defines an extremely unstable atmosphere (Pasquill category A) and the upper-limit of +5.560C is greater than the +40C that defines an extremely stable atmosphere (Pasquill category G). Therefore, the CPSES range envelopes- the atmospheric stability ranges specified in Table 1 of the
- proposed revision 1 of USNRC Regulatory Guide 1.23, " Meteorological Programs in Support of Nuclear Power Plants."
3.1 TUGC0 has performed an analysis to determine the vaiables that are needed for Accident Monitoring at CPSES and to determine the design criteria needed for these variables. This analysis and the Accident Monitoring design at CPSES meets the intent of Reg. Guide 1.97 Rev. 2.
n 4
- TUGC0 has performed a detailed comparison between the CPSES Accident
- Monitoring design and Reg. Guide 1.97 Rev. 2. The CPSES design complies
.with the guidance of Reg. Guide 1.97 Rev. 2 except as noted in our response to NRC question 032.110, as provided in the CPSES FSAR.
3.2 The list of Type A variables at CPSES is provided in Table 7.5-2 of the CPSES FSAR. The list in the interim evaluation omitted Narrow Range 4
Steam Generator Level and Steam Generator Blowdown Radiation.
.The following variables were listed as Type A by Table 7.5-2 but are no
, longer Type A:
a RCS Subcooling, Condenser Off-gas Radiation, Main Steamline Radiation, and Steam Generator Blowdown Radiation.
The 'CPSES design included Type A backup variables in a manner consistent with- the discussion of key and backup variables in section B of Reg. Guide 1.97 Rev. 2. These backup variables were assigned category 2 by the CPSES design. The NRC staff does not recognize Type A backup variable and
, requires 'that all Type A variables be category 1. Therefore, the four Type A backup _ variables listed above have been removed from the Type A list.
-3.3.1.1 Neutron Flux Range The interim evaluation found that the range provided by the CPSES_ design is not acceptable because it does not cover the range of 50% to 100% of rated power and the NRC Staff requires that neutron flux be indicated through 100%.
In order to comply with this requirement, the CPSES Accident Monitoring
- i. design will .be changed to include the Power Range Neutron Flux channels under the variable Neutron Flux (a type B, category 1 variable). The Power.
Range Neutron Flux channels comply with the category 1 requirements of the CPSES design (see the CPSES FSAR Chapter 7.5 and the response to NRC staff L
L
. question.032.110) except that the channels are not environmentally qualified to the post' accident environment inside containment following a design basis accident. This deviation is acceptable because power level will be in the power range for a very short period of time during those design basis accidents that result in a harsh environment inside containment.
3.3.1.2 Neutron Flux Environmental Qualification The variable, Neutron Flux, is a category 1 variable by the CPSES Accident Monitoring analysis and the guidance provided by Reg. Guide 1.97 Rev. 2.
The difficult and expensive backfit of_ upgrading the Source and Intermediate Range Neutron Flux Channels to category 1 requirements is not justified, however.
Neutron Flux was selected as the key Type B variable that provides the most direct indication of Reactivity Control. Of course, this variable actually indicates neutron flux and not reactivity. Neutron Flux is a (ynamic variable that depends on several variables altnough the trend of neutron flux is primarily controlled by reactivity. The CPSES Accident Monitoring design includes four backup variables for the type B function of Reactivity Control . These backup variables are RCS Hot Leg Temperature (Th), RCS Cold Leg Temperature (Tc),. Control Rod Position, and RCS Soluable Boron
- Concentration. These four variables, when taken together, provide a clear
- indication of the shutdown status of the core. The variables allow for the indication of changes in heat generation as well as changes in the main parameters that contribute to reactor reactivity. Knowledge of control rod position, boron concentration and RCS temperature ' determines actual reactor I
reactivity fairly precisely. _ In the long term, these backup variables are g the most accurate. indication of reactivity.
Because-full, proper and accurate indication is provided by these backup variables and because of the magnitude of the backfit to upgrade the Source
[ and Intermediate Neutron Flux channels to category 1, the CPSES design is
!' acceptable as is and upgrading should not be required by the NRC Staff.
i' u
.=
. With -NRC Staff agreement that the CPSES design is technically adequate for Accident Monitoring, the concerns over 10 CFR 50.49 are no longer appl icable. .
3.3.2 RCS Soluable Boron Concentration NUREG-0737, Item II.B.3 was closed out by CPSES SSER #6 (NUREG-0797),
Section 22.2, where the NRC staff concluded that the proposed post-accident
.. sampling : system at CPSES meets all of the criteria of Item II.B.3 of NUREG-0737 and is, therefore, acceptable. The CPSES design for the variable RCS Soluable Boron Concentration should be accepted based on this NUREG-0737, Item II.B.3 review.
3.3.4 Coolant Level in Reactor NUREG-0737, ' Item II.F.2 was closed out by CPSES SSER #6 (NUREG-0797),
Section-22.2, where the NRC staff concluded that the ICC detection system at CPSES is in conformance-with these requirements and that the
- implementation schedule is acceptable (with a . license condition that the
. system to measure coolant level in the' reactor be installed prior to startup for the second operating cycle) and, therefore, considers this issue. resolved. The CPSES design for the variable " Coolant Level in
' Reactor" should be accepted based on this NUREG-0737, Item II.F.2 review.
'3.3.5 Degrees of Subcooling
- This variable _ has been deleted from the list of Type A variables as discussed' under 3.2 above. Therefore category 2 should now be acceptable.
- 1he CPSES design for. Degrees of Subcooling should also be acceptable based
' on the NUREG-0737, Item II.F.2 review as discussed above under 3.3.4.
3.3.8 - Containment Pressure 4
This paragraph should be numbered 3.3.7.
. . - ._..u.------.-
. 3.3.12 Accumulator Tank Level and Pressure In evaluating the_ Type D variables needed to provide indication of the operation of the Emergency Core Cooling Systems, certain variables were found to be key variables (RWST Level, Safety Injection Flow, RHR Flow, Charging Pump Injection Flow, Containment Water Level, ECCS Valve Status and SI Accumulator Isolation Valve Status). In addition, this evaluation concluded that SI Accumulator Tank Level and-Pressure were good backup
,. variables. As Type D backup variables, both Reg. Guide 1.97 Rev. 2 and the CPSES analysis specify that these variables should be category 3.
The NRC staff requires that either SI Accumulator Tank Pressure or Level be a category 2, key variable. In order to cogly with this requirement, the CPSES design will be changed such that SI Accumulator Tank Pressure will i become a Type D key variable (category 2) while SI Accumulator Tank Level wi11' remain a Type D backup variable (category 3). This backfit will be l cogleted prior to startup for the second operating cycle for CPSES Unit 1
'or'as agreed upon with the NRC staff in a living schedule for CPSES Unit 1.
- 3.3.14 Pressurizer Heater Status
'In performing the Accident Monitoring analysis for CPSES, the key Type D variables for Pressurizer Level and Pressure Control were: PORY Status, Safety Valve Status, Pressurizer Level and RCS Pressure (WR). These variables provide the most direct indication of the operation of the
- Pressurizer Level and Pressure Control systems. In addition, Pressurizer Heater Breaker Position was chosen as a backup variable. Knowing uat a pressurizer heater breaker is closed and that the power supply is available provides good evidence that the' heaters are functioning. Knowing that the heaters are functioning is good backup information to RCS Pressure (WR) and potential diagnoistic information. The proper category for this variable is category 3.
Reg.l Guide '1.97 Rev. '2 calls for using the electric current to the
. pressurizer heaters as the monitored variable instead of breaker position.
Breaker position was available in the CPSES design while heater current was r
~
e not. The only apparent advantage to using current was that if there was a failure of some of the heaters, the operator might be able to evaluate what portion of the heaters were still operable. The accuracy of such an evaluation would be highly questionable an maybe even misleading. In a scenario where some of the heaters failed but the supply breaker did not trip, there is also a chance that high resistance faults could develope such that the circuit would draw current but not heat the coolant in the pressurizer. As a result of this type of logic, engineers performing the Accident Monitoring analysis for CPSES concluded that Pressurizer Heater Breaker Position was the correct variable for CPSES and that backfitting
' heater current channels was not technically required nor justified.
The NRC staff requires that the CPSES design includes electric current as category 2 Accident Monitoring parameters for those heaters required by the CPSES draft technical specification. In order to comply with this requirement, the CPSES design will be changed to add Pressurizer Heater Electric Current for each heater group as a Type D key variable (category 2). This backfit will be completed prior to startup for the second operating cycle for CPSES Unit 1 or as agreed upon with the NRC staff in a living schedule for CPSES Unit 1.
3.3.16 Steam Generator Pressure The variable at CPSES that provides information relative to steam generator pressure -is Main Steam 11ne Pressure. Main Steamline Pressure is sensed off the steamline just af ter it exists the steam generator, downstream of the steam flow restrictors and upstream of the Main Steam Isolation Yalves.
!- This means that the pressure sensed by this variable is very close to the same pressure seen by the Main Steam Safety Valves.
The Main Steam Safety Valves have different setting but per the final draft of the CPSES Technical Specifications, the highest setting is 1235 psig
+1%. The accumulation associated with these valves is 3%. That means that all the safety valves will be wide open at a pressure slightly less than 1285 psig. Based on this analysis, the range of 0 to 1300 psig is adequate for the Main Steamline Pressure variable.
z 3.3.17 Containment Atmosphere Temperature Per the containment analysis in Section 6.2 of the CPSES FSAR, the peak vapor temperature inside containment does not exceed 2700F except for certain main steamline break (SLB) accident scenarios. In the most severe SLB, the graph of temperature versus time shows that vapor temperature will exceed 3000F at about 50 to 60 seconds into the accident, the peak of 3340F will be reached about 90 seconds into the accident and that vapor tegerature will fall below 3000F at about 120 to 130 seconds into the accident. In other words, this is a rapid tegerature transient that could exceed 3000F for about one minute. The operator would probably not see this transient if it were displayed. And even if the operator did see the peak, all operations are automatic and the operator does not have the time or the systems available to take any benefical manual action in response to the peak.
Texas Utilities has reconsidered the range of this parameter based on the comments from the NRC Staff and the impact of the backfit. The CPSES design will be changed such that the range for Containment Atmosphere Temperature will be from 400F to 4000F to be in full cogliance with Regulatory Guide 1.97, Rev. 2 and to envelope all the transients at CPSES.
The backfit will be completed prior to startup for the second operating cycle for CPSES Unit 1 or as agreed upon with the NRC staff in a living schedule for CPSES Unit 1.
3.3.18 Containment Susp Water Temperature Where the CPSES Accident Monitoring analysis was performed, Containment Susp Water Temperature was not selected as either a key or a backup variable for any of the functions, systems or potential events being monitored. TUGC0 concluded that Containment Sump Water Temperature should not be an Accident Monitoring variable for CPSES.
The precise basis for the inclusion of this variable in Reg. Guide 1.97, Rev. 2, is not explicitly defined but it is possible that some plants may need to monitor this variable because of problems with the net positive L
suction head (NPSH) being provided for the ECCS pumps under certain accident conditions. A very conservative analysis of the WSH for ECCS pumps at CPSES was performed. This analysis is described in the CPSES FSAR
-in Section 6.3.2.2.10, Table 6.3-1, Figure 6.3-2 and the response to Lquestion 212.43. The conclusion of this analysis is that adequate NPSH is
- l. always provided to the ECCS pump in all modes (including recirculation when these pumps take suction on the containment susp) and using conservative
. a ssump tions. In other words, the FSH provided to the ECCS pumps has been shown to always be adequate at CPSES because of the system designs.
Monitoring containment susp water temperature will not be useful to the operator and may indeed be harmful (since it may take some of the operators time when he has more important actions or variables to be concerned with).
3.3.21 Condenser Air Removal System Exhaust - Noble Gas and Vent Flow Rates As discussed under section 3.2 above, the CPSES analysis no longer designates this variable as Type A. Therefore, category 2 is correct and should be acceptable to the NRC Staff.
The deviation. list in the CPSES submittal for Condenser Off-gas Radiation was that-the CPSES range was 10-5 to 10-1 pCf/cc Wille Reg. Guide 1.97, Rev. 2, under Type C variables, recommends a range of 10-6 to 10-2 pCi/cc.
The CPSES evaluation found 10-5 to 10-1 pCi/cc to be an adequate range for L CPSES and since this range covers a full four decades it should be acceptable to the'NRC staff on this basis, even though the absolute Ifmits of the range differ by one decade.
In the interim evaluation, the NRC staff compared the CPSES range for this varible to the range provide in Reg. Guide 1.97 Rev. 2 for Condenser Air Removal System Exhaust when used as a Type E variable. CPSES does not use Condenser Off-gas Radiation as a Type E variable. At CPSES, the off-gas l from the condensers passes _through the conmion plant vent and, in such designs, Reg. Guide 1.97 Rev. 2 allows that the detectors for the consion plant vent can be used to satisfy the Type E requirements established by the regulatory guide. The CPSES design uses these comunon plant vent i
L
detectors (range,10-6 to 105 pC1/cc) to meet the Reg. Guide 1.97 Rev. 2 Type E guidance.
3.3.22 Main Steamline Radiation As discussion in section 3.2 above, this variable is no longer Type A at CPSES and, therefore, category 2 should be acceptable.
3.3.24 Accident Sampling (Primary Coolant, Containment Air and Susp)
As described in section 3.3.2, the NRC Staff has accepted the CPSES design with respect to NUREG-0737, Item II.B.3. The CPSES Accident Monitoring design for the variables associated witn Accident Sampling should be accepted based on this NUREG-0737, Item II.B.3 review.
.g-t