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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
. Log # TXX-4159 File # 903.6 TEXAS UTILITIES GENERATING COMPANY M KYWAY Tt DWElf
- 100 Nt DHTII 4)t,lVE MTitEET, I..H. M1
- IBAI.I.AM TEXAN 73201 April 23, 1984 Dr. Harold R. Denton Director of Nuclear Reator Regulation U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION VALUE-IMPACT ANALYSIS FOR ELIMINATION OF LARGE PRIMARY LOOP PIPE RUPTURES
Dear Dr. Denton:
Enclosed please find forty (40) copies of the CPSES Value-Impact Analysis associated with the use of the alternate pipe break analysis to eliminate the need to postulate large primary loop pipe ruptures.
Should you have any questions concerning this matter please contact this office.
Sincerely, Homer C. Schmidt BSD:bjm Attachments
\
60 t\
8404250007 840423 PM ADOCK 05000445 A . _ .
PM _,
. .. - A. ..T. . - .. - . -
9
Page 1 of 12 VALUE-IMPACT AtALYSIS OF NOT ADDING PROfECfIVE STRLCfURES FOR IC IOOP BREAKS 1.0 Introduction his analysis presents a value-impact assessment of the mnsequences of exempting CPSES fran having to install protective structures to mitigate the effects of r<: actor coolant (RC) loop breaks. Wese protective structures include both jet shields to protect targets fran jet impingement loads and RC loop equipnent restraints. %is report relies upon trevious structural target interaction evaluations.
We proposed exemption will efficiently allocate public resources in the generation of electric power and decrease occupational radiation exposure.
Additional protective structures in already congested areas would incur large msts and significant occupational doses.
We safety concerns involve the effects of a postulated major double-ended pipe break in a reactor coolant loop. Unanalyzed loads on an essential structural or piping target could cause a loss of the safety function of the target.
2.0 Proposed Action aid Potential Alternatives It is troposed that CPSES be exempted from adding protective structures that either mitigate jet impingement loads on essential targets or restrain RC loop piping from damaging RC loop equipent after a IC loop line break.
mis proposal is based on consideration of occupational dose and cost 4 inpacts. We alternative muld be to require aiding trotective structures to withstand the jet impingement ~ loa 3s and restraint structures to protect BC loop equipnent. -
3.0 - Value-Impact Assessment Results Sunnary 'Ibtal Ebr 2 thits Value* (man-rem)
Occupational . exposure (operational) ' 156 man-rem nuch less than Public Health -0.8 man-rem Total Quantified Value 155.2 man-rem Impacts * ($)
-2,464,000
~
~ Jet Shield Inplementation Oost -
Restraint Shim 00st -
'276,840 Total Quantified Value --2,740,840.
and Fuel Ioad Delay .
and 25. weeks (unquantified)
~ ~
1*Value and inpact analyses based.on UnitL I. Pbr Unit 2 both the value and the negative irpact will increase (except Fuel Icad Delay which would be ~
minimal at this point).. ,
Page 2 of 12 4.0 Develognent of Qualification - Based on Unit 1 Data A.0 General Exposure md Cost Criteria A.1 Ebr Jet Impingement Protection his report applies to the following reactor coolant line breaks: (Ref. 1) 101 GA/B 201 GA/B 301 NA/B 401 GA/B 102 GA/B 202 GA/B 302 GA/B 402 G A/B 103 GA/B 203 GA/B 303 GA/B 403 GA/B 104 GA/B 204 GA/B 304 GA/B 404 GA/B 105 GA/B 205 GA/B 305 CWA /B 405 GA/B 106 GA/B 206 GA/B 306 GA/B 406 GA/B 107 IWR 207 IWR 307 IWR 407 IWR 1081 GA/B 2081 GA/B 3081 GA/B 4081 GA/B We essential targets of these breaks can be divided into three categories; structural; of Westinghouse pipiry3 smpe; and of Gibbs & Hill (G&H) piping scope. 'Ihe target / break interactions are identified below:
109 Structural Targets (Ref. 1)
Break Ibs. Targets Fbr Each Break 101, 102, 201, 202- 1 Pen. Sleeve 301, 302,.401, 402 103, 104, 105, 204, 6 Walls / Floors 303, 304, 305, 404, 405 106, 203, 206, 306 3 Walls / Floors 107, 207,'307, 407 -1 Wall / Floor 1081, 2081,.3081, 406 4 Walls / Floors.
205, 403, 4081 5 Walls / Floors s
4
- . , e
Page 3 of 12 27 Westinghouse Soape Piping Targets (includes valves) (Ref. 2)
Break Nos. Break Nas.
Target Line No. (Info. ) Target Line No. (Info.)
10" SI-1-103-2501R-1 103, 104, 105, 3" CS-1-235-2501R-1 106, 304 405, 106, 1081 10" RC-1-21-2501R-1 103, 104, 106, 6" SI-1-101-2501R-1 203, 205, 206 1081 ,
1-1/2" SI-1-199-2501R-1 103 10" RC-1-37-2501R-1 203, 206 4" RC-1-18-2501R-1 103 10" SI-1-180-2501R-1 204, 2081 12" RH-1-1-2501R-1 103, 104, 105, 3" CS-1-1-2501R-1 204, 2081 106, 405, ;
12" RC-1-7-2501R-1 104, 105, 405 2" RC-1-53-2501R 205, 303, 304 12" RH-1-2-2501R-1 104, 105, 403, 6" RC-1-29-2501R-1 207 404, 405, 406 10" SI-1-106-2501R-1 105, 405, 406 6" SI-1-102-2501R-1 303, 305, 306 12" RC-1-69-2501R-1 105, 404, 405 6" RC-1-46-2501R-1 303, 307 l
10" SI-1-181-2501R-1 303, 304 10" RC-1-78-2501R-1 403, 404, 406, 4081 10" RC-1-55-2501R-1 306' 10" SI-1-182-2501R-1 403, 404,
'405, 406, l- 4081 l
10" SI-1-105-2501R-2 3081 3" CS-1-79-2501R-2 403 6
14" RC-1-135-2501R-1 403 4" RC-1-75-2501R 403
- 6" BC-1-70-2501R-1 403 27 'Ibtal Westinghouse Scope Targets.
l r
Page 4 of 12 16 G&H Scope Piping Targets (includes valves) (Ref. 2)
Target Line Ib. Break Ibs. Target Line No. Break Ibs.
3/4" PS-1-6-2501R-2 103, 403, 404 2" MS-1-206-1303-2 1081 3/4" PS-1-28-2501R-2 103 2" MS-1-341-1303-2 1081
, 18" N-1-19-1303-2 104 18" N-1-18-1303-2 204 3/4" MS-1-6-2505-2 104, 105, 106 1 MS-045 & Tubing 2081 204, 205, 304 2" MS-1-199-1303-2 2081 305, 3081, 404 405 3/4" MS-16-2505-2 104, 105, 106 2" MS-1-339-1303-2 2081 3/4" MS-1-11-2505-2 104, 106, 203 18" N-1-17-1303-2 304 204, 205, 304 2" MS-1-218-1303-2 403 305, 3081, 404 405 '
3/4" MS-1-21-2505-2 104, 105, 106 18" N-1-20-1303-2 404 403, 405, 406 43 total G&H scope break-target interactions Amng the many assumptions in this analysis, it is first assmed that the breaks would rot be sielded at their murce. his is mfeasible per m earlier investigation. Therefore, any target requiring protecticm would be sielded at the target itself. Secondly, it is assumed that after the stress analyses on structural targets are cmpleted the result would be that there are no macceptable structural interactions. Eis is based on CPSES structural target interaction evaluations to date. Therefore, l no sields will be designed to protect structures from the reactor coolant line breaks.
As for the sove_ Westinghouse scope piping targets, Westinghouse has
( completed the stress analysis and has determined new support load data l for 195 supports. tese new loads must be malyzed to determine if jet loa 3 protection is required. Based on Westinghouse experience at other plants, the results of further malyses will be at nost the addition of a very few jet bmpers. It is therefore . assumed . for this analysis that no jet bepers will be required. Rese' assumptions have a conservative effect on both the value and impact results..
+- = g w w
" Page 5 of 12 2 ,
l i
A field walkdown of the above G&H piping targets was conducted to make general assumptions on the locations, sizes, configurations of the jet shields and their supporting members. It is assuned that there is one jet !
shield for each piping target even though the shield may be very large or j long to protect from several breaks and fran several directions.
%erefore, there would be only 16 shields to be aided. All shields would require periodic painting inspection and painting. '
l A.2 For IC RIuipment Restraints Wis malysis applies to the following restraints which are designed to prevent daage to RC loop equipment after a postulated line break: for each of 4 loops there are two restraints on the crossover leg elbows,1 restraint on the crossover leg vertical run, and 1 restraint on the stem generator inlet line elbow.
As these restraints are designed only to operate after m IC line break,- the gap' between the shim on the restraint and the piping must be maintained under
< all other conditions including sutdown, normal operating, seismic, ed
! water / stem hamner loadings (Ref. 3). Exempting CPSES fran these protective structures for m BC line break eliminates these murces. of possible unaccounted for interactions in cases where the gaps are not maintained.
B.0 Occupational-Exposure-Operational
' B.1 From Jet Shields Operational occupational exposure dose due to additionalt rotective
~s tructures is avoided by the proposed exemption to protecting essential targets from RC loop breaks. This dose would be incurred due to the
!' slowing down of normally anticipated work activities plus newly added routine maintenance of thesezjet shields in the steam generator-compartments.
I-To calculate the dose rate portion due to work slowdowns the normal manpower L traffic into the' stem generator compartments in the jet shield areas during reactor sutdowns in a plant year _(py) .is estimated as follows:
In' Service Inspection -- 18 men'9 1'* ea.
L Maintenance _(tube cleaning and plugging; .manway cover-handling; pump, valve, flange, '
~4 men 0 0.5 wk ea.
and tank-work) - ,
. Eddy Current Testing -
1 3' men 9 1.* ea..
Operations (supervise various' ' 3 men' e .1
- -activities)
Radiation Protection -- -3 men 911-* ea.
Mise?(painters, scaffold 11 men e 1
builders, laborers, inspectors-
- andl engineers);
TomL 40 man'* s/py A f
Page 6 of 12 7 .
We installation of these massive jet shields in congested areas would cause an assumed 3% increase in each workers time spent nearby. (bntributing factors to the slowdown include increased inaccessibility for personnel and equipnent to and from gimary system components, increased congestion between adjacent compartments, occasional jet shield removal and replacenent (often requiring polar crane time) to gain access to valves md equignent, and nore difficult Inusekeeping in areas of high contamination possibility. Thus the extra time in this radiation area due to slowdown is as follows:
.03 x 40 mm wks/py x 40 py = 48 mm wks me portion of increased dose rate for new routine maintenance inclu3es periodic paint inspection and repaintirv3 of the shields and would require support from scaffold builders, laborers, inspectors and radiation pcotection personnel. It is assumed that in the 40 year plant life the 16 shields will require painting 5 times each and require 8 workers at a conservative 15 manhrs per shield. %us the painting time over 40 years is as follows:
16 shields x 15 manbrs/ shield x 5 times x man * = 30 man As 40 manhrs hen, the total increased time in the shield area is the following:
TOTAL = 48 man * + 30 man * = 78 man *s Ibw it can be assaned that all workers will receive m average 25 mR/hr.
%is is inferred using m exposure rate of 50 mR/hr just at the outside channel head mmway cover (Ref. 4) where several workers will be located (near jet shields). However, many personnel will be located on the floor level where the exposure rate has fallen off very sharply with distance.
mus 25mR/hr is a realistic assumption causing the total increased dose due to the addition of the jet shields to be 78 man *s x 40 man hrs x 25 maem = 78 mm Itm mm
- man hr B.2 From FC Equipnent Restraints here is no significant occupational exposure dose to be saved at this.
point in thit 1 by exempting CPSES from fully installing tlw IC Equipnent
' Restraints.. m is is because with the exception of the properly sized shims the restraint structures are fully installed. While there would be same removal of pipe straps, pipe clamps and a few restraint kickers (most of which have had other items attached to them by now) so that the pipe can be fully insulated these individual items me int located such that they impede workers progress measurably. An exemption for thit 2 ~
however, would save the entire restraint structure from being . installed which would save several man-rems (unquantified for this study).
%ere is no requirement to inspect these restraints after plant operation nor will. they be painted m there is no ' exposure for those activities.
m
Page 7 of 12 i C.O Public Health It is assumed that the risk to public health of not adding jet shields and equipment restraints is similar to the risk of not adding modifications to mitigate asymmetric blowdown loads on Erimary system omnponents which is assessed in Ref. 5. mis analysis shows that the ridc to public health of the
' proposed exemption for Comanche Peak will be more conservative than the risk to public health determined in Ref. 5. his is acccm.plished by performing a simple weighted average population density calculation. This shows that the population, per individual, closest to the plant has a heavier worth the the population, per individual, furthest from the plant. i s
Ref. 5 used a unifonn population densi of 340 people per square mile (which i
.is an average of all.US nuclear power ant sites). From Ref. 6 using the 4 ctnulative populations projected for 1 90 (further contributirg to a !
conservative risk value) we get the following:
CUMULATIVE IOPUIATION !
(Mues trom site) ;
0-10 0-20 0-30 0-40 0-50 ;
17,930 37,843 120,827 594,707 1,198,040 he simple unweighted population density figure for the 50 mile radius is '
1,198,040 people W (50)2 miles = 152.5 people /sq. mile Men fran this data we em show the population is heavily distributed at the '
outer fringes of the 50-inile radius nodel as follows:
20-30 30-40 40-50 0-10 10-20 17,930 19,913 82,984 473,880 603,333 he areas that the above populations occupf as functions of' outer radius r x and a inner radiust x-1 Ax = 6 (rx -rx-1 )
+
The population densities' as a function of their distances from the-site shows there are more people in the outer sections of the 50 mile radius. This is figured: i POPUIATION IEEEITY(PBOPLE/SQ.MI) 0-10 10-20 20-30 ~30-40 40-50 ,
17,930 19,913 82,984 .473,880 603,333
- (1'02) *(20 2-10 2) . *(302-202 ) 5(40 2-302) Jtt50 2-402)
= 57.1 = 21.1 '~= 52.8 =-215.5 = 213.4 L Se simple weighted average population density is:
~
57.1 + 21.1 + 52.8 + 215.5 + 213.4
^
. 5
= 112 people /sq. mi.
Page 8 of 12
'Ib insure conservatism throughout the 40 year plant life, using the Ref. 5 values for the year 2020, the simple weighted merage population density is:
98.9 + 36.0 + 85.0 + 375.7 + 376.9 5
= 194.5 people /sq. mi.
Rese results show that in all cases for tin years 1990 and 2020 both the unweighted p>pulation densities md the simple weighted merage population densities the Cmanche Peu specific case will result in a much lower public health risk than the 340 people /q. mo. figure used in Ref. 5.
The other factor that makes the Conanche Peak ris less that the value of Ref.
5 is the considered number of plant years. Ref. 5 considered the number of remaining plant years for 16 plants at 23.6 yr. to give a total of 377 py.
As the number of plant years is a multiplying factor to give total risk then again the Cmanche Peak specific rid is less ard by a factor here of 9.4.
Assuming all the other assumptions of Ref. 5 apply to the O)manche Peak case, we know the value to public health of not adding protec':ive structures for RC loop breaks at Q)manche Peak will be much nore conservative than the Ibf. 5 nominal estimate of industry total (16 plants) public risk value of -3.4 man-rem.
Using the 9.4 factor, CPSES Public Health value much less than
-0.4 man-rem.
D.0 Implementation Cost D.1 Jet 911 elds We impact to CPSES of rot installing the jet shields is avoidance of analysis, design, fabrication, installation and maintenance costs as well as replacement power costs due to fuel load delay.
If jet shields were to be required the first step would be to perform the analyses for all break-target interactions to determine if a shield is necessary in each case. The costs of them are as follows:
- 1. Stress hialysis For 109 Structural - 48 man hrs. ea. @ $65/ man hr = $340,080.
Interactions For 43 G&H Piping - 16 man irs. ea. 0 $65/ man hr = $ 44,720.
Interactions For 195 Supports - 10 man hrs. ea. @ $55/ man hr = $107,250.
of Westinghouse Scope lines
'IorAL STRESS ANALYSES = $492,050.
Page 9 of 12 As discussed above, this analysis assumes the results of analysis on both structural targets and Westinghouse line supports to be that no shields or jet bumpers will be required. So, only the 16 G&H target shields would be f' designed. Wen, two conservative assumptions are made that minimize the time and cast factors. For one, the three stress analyses will be performed simultaneously by separate groups. We other is that as mon as a group of these targets which are located closely together (estimate 35% per field check) are malyzed then design may begin rather than waiting for all 43 analyses to be completed. It follows then the fuel loM delay (before start of design) due to analysis is (43 G&H Interactions x 0.35 x 16 man hrs / Interaction x 1 mm wk/40 man hrs] ; 3 workers = 2.0 man wks.
- 2. Design, Fabrication, and Installation In order to further facilitate minimum fuel load delay it is assmed that 3 designers and 1 checker can produce a total 3 designs in each 3 week period and alm that staffing is increased enough to complete installation of the 3 designs within the next 3 week period md m on. W is is a very conservative assumption as many problems could be encountered that would Md significant cost and delay. If the sove schedule is followed, then the delay attributable to design, fabrication md installation is Design of 3 shields - 3 weeks Design of 3 shields & install previous 3 shields - 3 weeks Design of 3 shielda & install revious I 3 shields - 3 weeks Design of 3 shields & install previous 3 shields - 3 weeks Design of 3 shields & install gevious 3 shields - 3 weeks Design of 1 shield & install previous 3 shields - 3 weeks Install Irevious 1 shield - 3 weeks
'Ibtal shields -16 Total time required -21 weeks costs for the design, fabrication and installation of those 16 shields is extrapolated from costs of previous shields. Designire costs will be the same as gesently encountered because the manpower mw available can support this schedule. However, fabrication ard installation durity heavy load periods muld require more staff. We number of Civil Engineers and drafters who check fabrication drawings and hilti bolt locations would double md an increase in CBI, welding md NDE personnel who initiate drawings, check, fabricate, install, inspect and paint would be required. Wese costs are Designers - design & dieck 16 shields @ $19,500 ea. = $312,000.
Civil Engr. - 4 men @ $44.44/mm hr. @ 40 man hrs /*
@ 18 wks = $127,987.
- 2 men 0 $44.44/ man hr. @ 40 mm hrs /*
@ 3 wks = $10,666.
Installation + materials = 16 shields x ($9400 CBI cost / shield + $1410 others cost / shield + $1410 materials) = $195,520.
Extra personnel for peak periods = $4500/Wc @ 15 wks = $ 67,500.
'Ibtal design, fabrication, installation $713,673.
Page 10 of 12 D.2 restraint Shim Installation he impact to CPSES of not installing the shims to complete the design of the RC loop equipnent restraints is avoidan of machining and installation costs as well as replacement power costs due to fuel load delay. 'Ihese o sts are as follows.
- 1. Offsite machining = $ 30,000
- 2. Manhours
- a. Craft - 140 manteurs @ $35/hr =$ 4,900
- b. Engineering - Westinghouse and site -
8 men @ 8 days @ 24 hrs / day 0 $75 avg. cost /hr = $115,200
'10tal Cost bhlm installation = 4IDU,IUU All shims are not required the pipe straps, pipe clamps, and my restraint kickers that were not dsed for other purirses could be removed so that the insulation could be patched. Estimated costs for these are:
- 1. Manhours-craft to remove straps, el , kickers -12 manhrs @
S35 =$ 420
- 2. Insulation
- a. Material =$ 60
- b. Craft time - 20 manhrs/ joint
@ 16 joints @ $35/manhr = $ 11,200.
'Ibtal (bst to Fully Insulate (amunt saved if shims required) 11,680.
Net Bestraint Shim Installation Oost
= $150,100 - $11,680 = 138,420.
to shim replacement alone will impact compartment closure and therefore building closure and therefore fuel load bt an estimated mnservative 2-weeks.
E.0 Maintenance Cbsts E.1 For Jet Shields As mentionedt reviously thez,e 16 shields will require periodic inspection and occassional repaintinq. 21s requires support personnel for a total of 8 workers for 5 paint jobi. ia the 40 year plant life. Assuming a time requirement of 15 man hours per shield and a continued manpower cast of
$22/mm hr. and not including material msts all of 411ch are conservative will yield the following:
16 shields x 15 manhrs/ shield x (5 times /40 yrs) x $22/ man hr
= $26,400 total painting costs
. - - . .. . - ~.
Page 11 of 12 0 E.2 Ebr Restraints No painting or other inspection of the restraints is required after the shims are first verified.
5.0 Conclusions he summary results fbr the value-impact assessment as shown below. We estimates for cost and dose indicate that the proposed action sinuld be recomended. Wese estimates do rot show negative benefits for either dose or cost. %e following observations can be made:
- This analysis assumed that if implementation of jet shields were required, a fuel load delay is preferable to installation during plant outages. We after Inwer work in containment would increase the occupational dose rate, require nore worker and support personnel time and still require some additional cbwntime leading to replacement power costs.
^
- Wis analysis does rot aidress values or impacts of accidental occupational exposure, public property nor onsite property effects. Ref. 4 values for these can be used as approximate figures for comparison.
Summary of Value-Impact Assessment Value Impact 152.2 man-Rem - $2,740,840 as well as 25 weeks fuel load delay to Unit 1.
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. . Page 12 of 12 REFERENCES
- 1. CPSES - Field Danage Study Group Field Walkdown Package of thit 1 Containment, Problem 149A, B, C, & D, Ibv. AB-0, 10-8-83.
- 2. WPr--6834,' Jet Impingement Ioals from ICL Breaks, T. R. Puryear to J. B. George, December 6,1983. ,
- 3. NUREG 2136 Effects of Ibstulated Event Devices on Ibrmal Operation ;
of Piping Systems in Nuclear Power Plants, May 1981.
- 4. Designers Raliation Exposure AIARA Manual, Westinghoum Electric Corp. Table 4-2, kv. 2 (Draft), 1982.
- 5. Leak Before- Break Analysis by Pacific Wrthwest Iaboratory as Attachment to Enclosure 4, Ibgulatory . Analysis of Mechanistic Fracture Evaluation of Reactor Coolant Piping A-2 Westinghouse Owners Group Plants, WCAP 9558, Rev. 2, May.1982.
- 6. CPSES Final Safety Analysis Report, Table 2.1-5, Rev. O.
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