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Category:CORRESPONDENCE-LETTERS
MONTHYEARTXX-9924, Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span1999-10-22022 October 1999 Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span ML20217M5711999-10-20020 October 1999 Forwards Insp Repts 50-445/99-15 & 50-446/99-15 on 990822- 1002.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy TXX-9923, Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred1999-10-15015 October 1999 Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred ML20217E7951999-10-12012 October 1999 Forwards COLR for Unit 1,Cycle 8,per TS 5.6.5 ML20212L2891999-10-0101 October 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals. Purpose of GL Was to Obtain Info That Would Enable NRC to Verify That Condition of Licensee SG Internals Comply with Current Licensing Bases TXX-9922, Forwards Revised COLR, for Cycle 5 for Unit 21999-10-0101 October 1999 Forwards Revised COLR, for Cycle 5 for Unit 2 ML20216J5571999-10-0101 October 1999 Provides Final Response to GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps ML20212G0721999-09-24024 September 1999 Forwards Rev 4 to Augmented Inservice Insp Plan for CPSES, Unit 1. Future Changes & Revs to Unit 1 Augmented Inservice Insp Plan Will Be Available on Site ML20212H0461999-09-24024 September 1999 Forwards Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 990820 ML20212F7481999-09-24024 September 1999 Forwards SER Authorizing Relief from Exam Requirement of 1986 Edition ASME Code,Section XI Pursuant to 10CFR50.55a(a)(3)(ii) for Relief Request A-3 & 10CFR50.55a(g)(6)(i) for Relief Requests B15,16,17 & C-4 ML20212F1041999-09-23023 September 1999 Requests That NRC Be Informed of Any Changes in Scope of Y2K System Deficiencies Listed or Util Projected Completion Schedule for Comanche Peak Steam Electric Station,Units 1 & 2 ML20212E6661999-09-21021 September 1999 Advises That Info Contained in Application & Affidavit, (CAW-99-1342) Re WCAP-15009,Rev 0, Comache Peak Unit 1 Evaluation for Tube Vibration Induced Fatigue, Will Be Withheld from Public Disclosure ML20212D9111999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of CPSES & Did Not Identify Any Areas in Which Performance Warranted Insp Beyond Core Insp Program.Core Insp Plan at Facility Over Next 7 Months.Insp Plan Through March 2000 Encl ML20212A7601999-09-14014 September 1999 Forwards Insp Repts 50-445/99-14 & 50-446/99-14 on 990707-0821.Four Violations Occurred & Being Treated as Ncvs.Conduct of Activities Was Generally Characterized by safety-conscious Operations & Sound Radiological Controls TXX-9921, Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC1999-09-10010 September 1999 Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC ML20211P3761999-09-0707 September 1999 Ack Receipt of Ltr Dtd 990615,transmitting Rev 30 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20211L9871999-09-0303 September 1999 Forwards Rev 31 to Technical Requirements Manual. All Changes Applicable to Plants Have Been Reviewed Under Util 10CFR50.59 Process & Found Not to Include Any USQs TXX-9915, Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl1999-09-0303 September 1999 Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl ML20211K2231999-08-31031 August 1999 Forwards Txu Electric Comments of Rvid,Version 2 ML20211J3801999-08-27027 August 1999 Forwards Corrected TS Page 3.8-26 to Amend 66 to Licenses NPF-87 & NPF-89,respectively.Footnote on TS Page 3.8-26 Incorrectly Deleted ML20211G7301999-08-26026 August 1999 Forwards Revs 29 & 30 to CPSES Technical Requirements Manual (Trm). Attachments 1 & 2 Contain Description of Changes for Revs 29 & 30 Respectively ML20211G1081999-08-26026 August 1999 Responds to NRR Staff RAI Re Util Mar 1999 Submittal for NRC Review & Approval of Changes to CPSES Emergency Classification Procedure ML20211G3441999-08-25025 August 1999 Forwards Response to NRC RAI on LAR 98-010 for Cpses,Units 1 & 2.Communication Contains No New Licensing Commitments Re Cpses,Units 1 & 2 ML20211B2861999-08-18018 August 1999 Forwards Insp Repts 50-445/99-13 & 50-446/99-13 on 990720- 23.No Violations Noted.Insp Included Implementation of Licensee Emergency Plan & Procedures During Util Biennial Emergency Preparedness Exercise ML20211C4661999-08-18018 August 1999 Discusses Proprietary Info Re Thermo-Lag.NRC Treated Bisco Test Rept 748-105 as Proprietary & Withheld It from Public Disclosure,Iaw 10CFR2.790 ML20210U3981999-08-17017 August 1999 Forwards Monthly Operating Repts for July 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs or SVs for Plant Occurred ML20211C0991999-08-17017 August 1999 Forwards Rev 3 to ASME Section XI ISI Program Plan,Unit 2 - 1st Interval, Replacing Rev 2 in Entirety ML20211C4571999-08-16016 August 1999 Forwards Omitted Subj Page of Contractor TER TXX-9919, Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 9908021999-08-16016 August 1999 Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 990802 ML20210R6561999-08-13013 August 1999 Forwards Response to NRR 990805 Telcon RAI Re License Amend Request 98-010,to Increase Power for Operation of CPSES Unit 2 to 3445 Mwth & Incorporating Addl Changes Into Units 1 & 2 TS ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210S6411999-08-12012 August 1999 Informs That Wg Guldemond,License SOP-43780,is No Longer Performing Licensed Duties.Discontinuation of License Is Requested ML20210R2221999-08-12012 August 1999 Forwards Insp Repts 50-445/99-10 & 50-446/99-10 on 990510-0628.Violations Noted & Being Treated as Ncvs, Consistent with App C of Enforcement Policy ML20210N1101999-08-0404 August 1999 Provides Supplemental Info to Util 990623 License Amend Request 99-005 Re Bypassing DG Trips.Info Replaces Info Contained in Subject Submittal in Attachment 2,Section II, Description of TS Change Request ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210J2301999-08-0202 August 1999 Forwards Amend 96 to CPSES Ufsar.Replacement of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,Rev 2 ML20210J6071999-08-0202 August 1999 Forwards line-by-line Descriptions of Changes in Amend 96 to CPSES UFSAR Transmitted by Util Ltr TXX-99166,dtd 990802. Replacment of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,rev 2 TXX-9916, Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 9907271999-08-0202 August 1999 Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 990727 TXX-9918, Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-9906301999-08-0202 August 1999 Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20210K2321999-07-29029 July 1999 Forwards Insp Repts 50-445/99-12 & 50-446/99-12 on 990530-0710.No Violations Noted ML20210G5861999-07-29029 July 1999 Forwards fitness-for-duty Program Performance Data for Six Month Period of Jan-June 1999 ML20210J0121999-07-27027 July 1999 Forwards Summary of Methodology for Determination of NDE Measurement Uncertainty,In Response to Recent Discussions with NRC Re LAR 98-006 Concerning Rev to SG Tube Plugging Criteria TXX-9917, Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES1999-07-26026 July 1999 Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES ML20210F3121999-07-26026 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, ML20210D8231999-07-23023 July 1999 Forwards Safety Evaluation of Relief Requests Re Use of 1998 Edition of Subsections IWE & Iwl of ASME Code for Containment Insp ML20210D3211999-07-21021 July 1999 Provides List of Estimates of Licensing Actions,In Response to Administrative Ltr 99-02,dtd 990603 ML20210C2931999-07-21021 July 1999 Supplements 880323 Response to NRC Bulletin 88-02, Rapidly Propagating...Sg Tubes, Non-proprietary WCAP-15010 & Proprietary Rev 0 to WCAP-15009, CP Unit 1 Evaluation for Tube Vibration... Encl.Proprietary Rept Withheld ML20209H0111999-07-16016 July 1999 Forwards Relief Request C-4 to CPSES Unit 2 ISI Program for Approval ML20210C3331999-07-16016 July 1999 Forwards Exam Repts 50-445/99-301 & 50-446/99-301 on 990618- 24.Exam Included Evaluation of Six Applicants for Senior Operator Licenses ML20209H2551999-07-16016 July 1999 Forwards ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2 & Containment ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2,per ASME Boiler & Pressure Vessel Code,Section Xi,Paragraph IWA-6230 1999-09-07
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARTXX-9924, Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span1999-10-22022 October 1999 Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span TXX-9923, Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred1999-10-15015 October 1999 Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred ML20217E7951999-10-12012 October 1999 Forwards COLR for Unit 1,Cycle 8,per TS 5.6.5 ML20216J5571999-10-0101 October 1999 Provides Final Response to GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps TXX-9922, Forwards Revised COLR, for Cycle 5 for Unit 21999-10-0101 October 1999 Forwards Revised COLR, for Cycle 5 for Unit 2 ML20212G0721999-09-24024 September 1999 Forwards Rev 4 to Augmented Inservice Insp Plan for CPSES, Unit 1. Future Changes & Revs to Unit 1 Augmented Inservice Insp Plan Will Be Available on Site ML20212H0461999-09-24024 September 1999 Forwards Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 990820 TXX-9921, Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC1999-09-10010 September 1999 Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC ML20211L9871999-09-0303 September 1999 Forwards Rev 31 to Technical Requirements Manual. All Changes Applicable to Plants Have Been Reviewed Under Util 10CFR50.59 Process & Found Not to Include Any USQs TXX-9915, Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl1999-09-0303 September 1999 Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl ML20211K2231999-08-31031 August 1999 Forwards Txu Electric Comments of Rvid,Version 2 ML20211G1081999-08-26026 August 1999 Responds to NRR Staff RAI Re Util Mar 1999 Submittal for NRC Review & Approval of Changes to CPSES Emergency Classification Procedure ML20211G7301999-08-26026 August 1999 Forwards Revs 29 & 30 to CPSES Technical Requirements Manual (Trm). Attachments 1 & 2 Contain Description of Changes for Revs 29 & 30 Respectively ML20211G3441999-08-25025 August 1999 Forwards Response to NRC RAI on LAR 98-010 for Cpses,Units 1 & 2.Communication Contains No New Licensing Commitments Re Cpses,Units 1 & 2 ML20210U3981999-08-17017 August 1999 Forwards Monthly Operating Repts for July 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs or SVs for Plant Occurred ML20211C0991999-08-17017 August 1999 Forwards Rev 3 to ASME Section XI ISI Program Plan,Unit 2 - 1st Interval, Replacing Rev 2 in Entirety TXX-9919, Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 9908021999-08-16016 August 1999 Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 990802 ML20210R6561999-08-13013 August 1999 Forwards Response to NRR 990805 Telcon RAI Re License Amend Request 98-010,to Increase Power for Operation of CPSES Unit 2 to 3445 Mwth & Incorporating Addl Changes Into Units 1 & 2 TS ML20210S6411999-08-12012 August 1999 Informs That Wg Guldemond,License SOP-43780,is No Longer Performing Licensed Duties.Discontinuation of License Is Requested ML20210N1101999-08-0404 August 1999 Provides Supplemental Info to Util 990623 License Amend Request 99-005 Re Bypassing DG Trips.Info Replaces Info Contained in Subject Submittal in Attachment 2,Section II, Description of TS Change Request TXX-9918, Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-9906301999-08-0202 August 1999 Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20210J2301999-08-0202 August 1999 Forwards Amend 96 to CPSES Ufsar.Replacement of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,Rev 2 ML20210J6071999-08-0202 August 1999 Forwards line-by-line Descriptions of Changes in Amend 96 to CPSES UFSAR Transmitted by Util Ltr TXX-99166,dtd 990802. Replacment of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,rev 2 TXX-9916, Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 9907271999-08-0202 August 1999 Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 990727 ML20210G5861999-07-29029 July 1999 Forwards fitness-for-duty Program Performance Data for Six Month Period of Jan-June 1999 ML20210J0121999-07-27027 July 1999 Forwards Summary of Methodology for Determination of NDE Measurement Uncertainty,In Response to Recent Discussions with NRC Re LAR 98-006 Concerning Rev to SG Tube Plugging Criteria TXX-9917, Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES1999-07-26026 July 1999 Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES ML20210F3121999-07-26026 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, ML20210C2931999-07-21021 July 1999 Supplements 880323 Response to NRC Bulletin 88-02, Rapidly Propagating...Sg Tubes, Non-proprietary WCAP-15010 & Proprietary Rev 0 to WCAP-15009, CP Unit 1 Evaluation for Tube Vibration... Encl.Proprietary Rept Withheld ML20210D3211999-07-21021 July 1999 Provides List of Estimates of Licensing Actions,In Response to Administrative Ltr 99-02,dtd 990603 ML20209H2551999-07-16016 July 1999 Forwards ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2 & Containment ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2,per ASME Boiler & Pressure Vessel Code,Section Xi,Paragraph IWA-6230 ML20209H0111999-07-16016 July 1999 Forwards Relief Request C-4 to CPSES Unit 2 ISI Program for Approval ML20209G0721999-07-13013 July 1999 Forwards Monthly Operating Repts for June 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs of SV Occurred During Reporting Period ML20209F0681999-07-0909 July 1999 Informs That Effective 990514,TU Electric Formally Changed Name to Txu Electric.Change All Refs of TU Electric to Txu Electric on Correspondence Distribution Lists ML20209E0421999-07-0909 July 1999 Forwards Response to NRC Request for Addl Info on LAR 98-010.Attachment 1 Is Affidavit for Info Supporting LAR 98-010 ML20209B6021999-06-30030 June 1999 Submits Second Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Readiness Disclosure for Reporting Status of Facility Y2K Readiness Encl ML20195J6981999-06-15015 June 1999 Provides Addl Info Related to Open Issue,Discussed in 990610 Conference Call with D Jaffe Re ISI Program Relief Request L-1 Submitted by Util on 980220 ML20196A4921999-06-15015 June 1999 Forwards Rev 30 to Physical Security Plan.Rev Withheld,Per 10CFR73.21 ML20195J0491999-06-14014 June 1999 Submits Response to RAI Re Implementation of 1.0 Volt Repair Criteria ML20195J0651999-06-14014 June 1999 Submits Response to RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves 05000445/LER-1999-001, Forwards LER 99-001-00, Some Electrical Contacts for RCS Pressure Relief Valves Were Not Included in Surveillance Testing Procedures. New Licensing Commitments Identified in Attachment 11999-06-0808 June 1999 Forwards LER 99-001-00, Some Electrical Contacts for RCS Pressure Relief Valves Were Not Included in Surveillance Testing Procedures. New Licensing Commitments Identified in Attachment 1 ML20195F0091999-06-0808 June 1999 Forwards Response to RAI Re Units 1 & 2 ISI Program for Relief Requests E-1 & L-1.Communication Contains No New Licensing Basis Commitments Re Cpses,Units 1 & 2 ML20207E1921999-05-28028 May 1999 Submits Updated Request for NRC Staff to Review & Approve Certain Changes to CPSES Emergency Plan Submitted in 981015 & s Prior to Changes Being Implemented at CPSES ML20207E1711999-05-28028 May 1999 Supplements 990526 LAR 99-004 as TU Electric Believes Extingency Exists in That Proposed Amend Was Result of NOED Granted to Prevent Shudown of CPSES Unit 1 ML20207D9841999-05-26026 May 1999 Requests That NRC Exercise Enforcement Discretion to Allow Cpses,Unit 1 to Remain in Mode 1,power Operation,Without Having Performed Svc Test,Per SR 4.8.2.1d on Unit 1 Battery BT1ED2 ML20195B6351999-05-25025 May 1999 Submits Response to RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves TXX-9912, Forwards Txu Electric (Formerly TU Electric) CPSES Emergency Preparedness Exercise Scenario Manual for 990721-22,Graded Exercise1999-05-21021 May 1999 Forwards Txu Electric (Formerly TU Electric) CPSES Emergency Preparedness Exercise Scenario Manual for 990721-22,Graded Exercise ML20206U1981999-05-20020 May 1999 Forwards Form 10K Annual Rept,Per 10CFR50.71(b). Communication Contains No New Licensing Basis Commitments Re Cpses,Units 1 & 2 ML20196L1931999-05-20020 May 1999 Forwards MOR for Apr 1999 for Cpses,Units 1 & 2.During Reporting Period There Have Been No Failures or Challenges to Power Operated Relief Valves or Safety Valves TXX-9911, Forwards non-proprietary & Proprietary Responses to RAI Re LAR 98-010 by Incorporating Attached Changes Into CPSES Unit 2 OL NPF-89 & CPSES Units 1,OL NPF-87 & 2 TS to Increase Licensed Power.W & Caldon Proprietary Responses Withheld1999-05-14014 May 1999 Forwards non-proprietary & Proprietary Responses to RAI Re LAR 98-010 by Incorporating Attached Changes Into CPSES Unit 2 OL NPF-89 & CPSES Units 1,OL NPF-87 & 2 TS to Increase Licensed Power.W & Caldon Proprietary Responses Withheld 1999-09-03
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059K6141990-09-17017 September 1990 Submits Documentation of 900906 Telcon Re Addl Util Candidate for Licensed Operator Generic Fundamentals Exam Section ML20059G8761990-09-10010 September 1990 Forwards Rev 8 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML20059F8461990-09-0404 September 1990 Responds to NRC Re Violations Noted in Insp Repts 50-445/90-22 & 50-446/90-22 on 900606-0705.Corrective action:OPT-467A Changed to Provide Addl Prerequisite Info Re Solid State Protection Sys Switch Lineup During Testing ML20059E4981990-08-31031 August 1990 Forwards Revised Radial Peaking Factor Limit Rept for Cycle 1 Per Tech Specs Through Amend 1 & ML20059E4201990-08-30030 August 1990 Forwards Objectives & Guidelines for 1990 Emergency Preparedness Exercise Scheduled for 901113 ML20028G8281990-08-29029 August 1990 Forwards Comanche Peak Unit 1 Semiannual Radioactive Effluent Release Rept,900403-0630 & ODCM TXX-9030, Forwards Endorsements 40 & 4 to Nelia Policy NF-274 & Maelu Policy M-90,respectively & Endorsements 10,11,12,13,14 & 15 to Maelu Policy MF-1311990-08-27027 August 1990 Forwards Endorsements 40 & 4 to Nelia Policy NF-274 & Maelu Policy M-90,respectively & Endorsements 10,11,12,13,14 & 15 to Maelu Policy MF-131 ML20059F4381990-08-23023 August 1990 Forwards Public Version of Revised Emergency Plan & Corporate Emergency Response Procedures,Consisting of Rev 1 to EPP-313,Rev 7 to CERP-101,Rev 7 to CERP-102 & Revised Forms.W/Dh Grimsley 900906 Release Memo TXX-9029, Responds to NRC Re Violations Noted in Insp Repts 50-445/89-57 & 50-446/89-57.Corrective Actions:Storage Facilities for Instrumentation & Control Work Packages Improved to Provide Acceptable Protection for Documents1990-08-20020 August 1990 Responds to NRC Re Violations Noted in Insp Repts 50-445/89-57 & 50-446/89-57.Corrective Actions:Storage Facilities for Instrumentation & Control Work Packages Improved to Provide Acceptable Protection for Documents ML20058P0571990-08-13013 August 1990 Forwards, Comanche Peak Steam Electric Station Unit 1 Control Room Simulator 10CFR55 Certification Initial Rept ML20058N2311990-08-0909 August 1990 Forwards First Half 1990 fitness-for-duty Program Performance Data,Per 10CFR26.71(d).Point of Contact for Personnel,Random Testing Program Results & Confirmed Positive Tests Summary & Mgt Summary Included in Data ML20059A5831990-08-0404 August 1990 Responds to Info Request Made During 900802 Meeting Re Inadvertent Safety Injections on 900726 & 30 & Results of 100% Power Plateau Testing TXX-9024, Provides Status of Exam Activity & Revised Completion Schedule for Portion of Exam.Util Deferred Preoperational Testing of Facility Spent Fuel Pool Cooling & Cleanup Sys Until Prior to First Off Loading of Spent Fuel1990-08-0303 August 1990 Provides Status of Exam Activity & Revised Completion Schedule for Portion of Exam.Util Deferred Preoperational Testing of Facility Spent Fuel Pool Cooling & Cleanup Sys Until Prior to First Off Loading of Spent Fuel TXX-9022, Forwards Detailed Descriptions of Changes in Amend 79 to FSAR for Comanche Peak Steam Electric Station1990-07-31031 July 1990 Forwards Detailed Descriptions of Changes in Amend 79 to FSAR for Comanche Peak Steam Electric Station TXX-9027, Responds to NRC Re Violations Noted in Insp Repts 50-445/90-19 & 50-446/90-19.Corrective Action:Specific Activity within Tech Spec Limits.No Further Corrective Action Required1990-07-30030 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-445/90-19 & 50-446/90-19.Corrective Action:Specific Activity within Tech Spec Limits.No Further Corrective Action Required ML20055J1571990-07-27027 July 1990 Submits Info Re Replacement of Borg-Warner/Intl Pump,Inc Check Valve Swing Arms,Per .Swing Arms in ASME Code Class 2 Check Valves Will Be Replaced During First Refueling Outage ML20056A0461990-07-24024 July 1990 Requests Regional Waiver of Compliance for Containment Pressure Transmitter 1-PT-934 During Coming Outage TXX-9023, Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. No Subj Transmitters in Existence at Facility1990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. No Subj Transmitters in Existence at Facility ML20055G6351990-07-17017 July 1990 Submits Results of Remote Shutdown Panel Environ Survey ML20055F9391990-07-13013 July 1990 Advises That Operators Have Gained Significant Experience in Operating Plant Under Wide Range of Conditions & Have Demonstrated Necessary Proficiency to Safely Operate Unit ML20055F9371990-07-13013 July 1990 Submits Info Re Revised Acceptance Criteria for THERMO-LAG Fire Barrier,Per 900705 Telcon.On Exposure to Heat Flux at Surface of Barrier,Listed Mechanisms Activated.Fire Testing Demonstrates That Panels Qualified W/Variation in Thickness ML20044A7001990-06-26026 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Util Will Implement for Unit 2 Activities Performed for Unit 1 ML20044A1411990-06-20020 June 1990 Forwards Endorsements 4 & 5 to Nelia Certificate N-90, Endorsements 5 & 6 to Maelu Certificate M-90 & Endorsements 34,35,36,37,38 & 39 to Nelia Policy NF-274 ML20043H7031990-06-18018 June 1990 Discusses Mod/Rework to Auxiliary Feedwater Sys Check Valves Mfg by Bw/Ip Intl,Inc.All But One Affected Check Valve modified.Motor-driven Auxiliary Feedwater Pump Discharge Valve Check Valve Body Replaced ML20043H2181990-06-15015 June 1990 Forwards Response to 900515 Request for Addl Info on Emergency Preparedness.Ongoing Emergency Preparedness Programs Address Concerns Raised by Citizens for Fair Util Regulation ML20043G3131990-06-15015 June 1990 Forwards Addl Info Re Pressurizer Surge Line Thermal Stratification & leak-before-break Evaluation & Nonproprietary Suppl 3 to WCAP-12247, Supplementary Assessment... & Proprietary Suppl 3 to WCAP-12248 ML20043C5671990-06-0101 June 1990 Discusses Identification of Slave Relays Tested Using Alternative Methodology,Per 900402 Commitment.Encl Tabulation Identifies Test Type,Applicable Procedures & Equipment & Impact of Improper Documentation ML20043E7131990-06-0101 June 1990 Responds to NRC 900517 Notice of Violation & Imposition of Civil Penalty in Amount of $25,000.Corrective Action:Qc Mgt Counseled Level III Inspector & QC Supervisor on Importance of Good Communications W/Receipt Inspectors ML20043C4501990-05-31031 May 1990 Advises That Util Revised FSAR Section 15.1.2 & Question/ Response 32.108,per 10CFR50.59 ML20043B5471990-05-25025 May 1990 Provides Status of Facility Design & Const Activities,Per Request.Detailed Design Work Will Resume in June 1990.Const Activities Expected to Increase Signficantly by Jan 1991 ML20043B5481990-05-23023 May 1990 Provides Clarification of 890710 Commitment Re Power Ascension Program.Cooldown Portion of Remote Shutdown Test Performed During Preoperational Testing,Per FSAR & Reg Guide 1.68.2 ML20043D1711990-05-21021 May 1990 Forwards Public Version of Revised Emergency Plan Procedures,Including Rev 8 to EPP-109,Rev 7 to EPP-112,Rev 4 to EPP-116 & Rev 6 to EPP-121.W/DH Grimsley 900604 Release Memo TXX-9018, Advises of Completion of Implementation of Requirements of Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety- Related Equipment1990-05-21021 May 1990 Advises of Completion of Implementation of Requirements of Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety- Related Equipment ML20043B0981990-05-15015 May 1990 Forwards Radial Peaking Factor Limit Rept for Cycle 1, Containing F(Xy) Limits for All Core Planes Containing Bank D Control Rods & All Unrodded Core Planes ML20042F2851990-05-0303 May 1990 Supplemental Response to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. ML20042F3861990-05-0303 May 1990 Responds to NRC 900410 Ltr Re Violations Noted in Insp Repts 50-445/90-10 & 50-446/90-10 on 900206-07 & 0226-0302. Corrective Action:Memo Issued Emphasizing That Discrepancies Should Be Brought to Attention of Site Organizations ML20042F3021990-05-0202 May 1990 Responds to NRC 900402 Ltr Re Violations Noted in Insp Repts 50-445/89-23 & 50-446/89-23.Util Does Not Believe That Circumstances Described in 900402 Ltr Constitutes Violation of 10CFR50.9(a) ML20042F3051990-05-0202 May 1990 Provides Revised Response to Generic Ltr 88-17 Re Loss of DHR ML20042E4581990-04-12012 April 1990 Responds to Inconsistencies in Terminology & Labelling Identified During NRC 890118 & 19 Audit of Facility Dcrdr. Util Believes Control Room Inventory Requirement of Suppl 1 to NUREG-0737,satisfied ML20042E0701990-04-10010 April 1990 Discusses 900305 Meeting W/Nrc in Rockville,Md Re Offsite Power Availability for Automatic Switch Co Solenoids for MSIV in Event of Nonmechanistic Main Steam Line Crack in Superpipe Region ML20012F5011990-04-0303 April 1990 Forwards Corrections to 891016 Response to Emergency Diesel Generator Engine Requirements.Lengths of Two Pairs of Bolts Above Crankpin Shall Be Measured Ultrasonically Before Detensioning & Disassembly of Bolts ML20012F3221990-04-0202 April 1990 Discusses ESF Sys Slave Relay Alternate Test Methodology. Implementation Schedule for Design Mods to Relay Will Be Submitted by 900601 ML20042D8081990-03-29029 March 1990 Forwards Proposed Change to FSAR Section 13.4 Re Station Operations Review Committee.Similar Change Submitted in 900328 Ltr for Chapter 6 of Facility Tech Specs ML20012F0411990-03-28028 March 1990 Forwards marked-up Pages of Facility Draft Tech Specs & Bases (NUREG-1381) Provided W/Low Power OL ML20012E6051990-03-27027 March 1990 Forwards Endorsements 1-4 to Maelu Certificate M-90, Endorsements 1-9 to Maelu Policy MF-131,Endorsements 29-33 to Nelia Policy NF-274 & Endorsements 1-3 to Nelia Certificate N-90 ML20012E6531990-03-27027 March 1990 Provides Final Response to Reporting Requirement 2 of NRC Bulletin 88-008, Thermal Stresses in Piping Connected to RCS, for Unit.Nde Requirements of Action 2 Not Considered Applicable to Unit ML20012E1911990-03-23023 March 1990 Forwards Comanche Peak Steam Electric Station Unit 1 Cycle 1 Startup Physics Tests Control Rod Worth Predictions Utilizing TU Electric Control Rod Swap Methodology. ML20012E1581990-03-23023 March 1990 Clarifies 880624 Response to NRC Generic Ltr 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants. ML20012D0201990-03-19019 March 1990 Advises That Allegations Provided to NRC by Former Util Employee Unsubstantiated,Based on Investigation by Util Safeteam Organization ML20012E2181990-03-19019 March 1990 Responds to Generic Ltr 89-19 Re USI A-47, Safety Implication of Control Sys in LWR Nuclear Power Plants. Util Determined That Loss of safety-related Inverters 1 or 2 Would Involve Coincidental Opening of Main Feedwater Valves 1990-09-04
[Table view] |
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Log # TXX-6848
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File # 909.5
= = 10010 clo 7UELECTRIC Ref # 10CFR50.34(b) i wmun c. couna October 9, 1987 i Emutive Vnt Presiderrt V. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
D0CKET NOS. 50-445 AND 50-446 FIRE PROTECTION PROGRAM ADVANCE SUBMITTAL OF FSAR UPDATE
REFERENCE:
- 1) Letter logged TXX-6365 from W. G. Counsil to the NRC dated April 1, 1987 Gentlemen:
In preparation for an NRC review of the CPSES Fire Protection Program, we have enclosed an advance copy of a change to the CPSES FSAR sections relative to the CPSES Fire Protection Program. This change reflects the new computerized format described in reference 1. In order to adopt the new computerized format for the table in subsection 9.5.1.6.2 of the FSAR, (comparing the CPSES Fire Protection Program with APCSB 9.5-1, Appendix A), we no longer have the applicable sections of APCSB 9.5-1, Appendix A in the left column of the page with the corresponding description of the CPSES Fire Protection Program in the right column. Instead, we have moved the applicable sections of APCSB 9.5-1, Appendix A in front of the corresponding descriptions of the CPSES Fire Protection Program. This format change also provides clearer, easier reading of the CPSES Fire Protection Program.
This FSAR update includes changes addressing the following general topics:
(1) revised fire safe shutdown analyses, (2) revised fire hazards analysis, (3) organizational changes, and (4) design modifications to CPSES.
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During our review of the new computerized format of the fire protection sections of the FSAR, we noted and corrected several errors in our reproduction of APCSB 9.5-1, Appendix A.
l We plan to submit these changes in'a future Amendment to the FSAR.
Very truly yours, V/VX W. G. Counsil JDS/mih -
Enclosure-Attachment c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) l l
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Attachment to.TXX-6848 October 9, 1987 Page 1 of 13 FSAR Page Description 1.2-23 Correction: Removes description of fire protection system separation in relation to seismic category 1 equipment. i
.Section 3.2.2 contains the technical description of how I the fire protection system meets the Class 5 criteria, j l
1.2-24 Correction: Changed description of fire detectors to !
reflect the fact that ionization detectors are the only I devices with indicating lamps in the base of the unit.
This is not'a requirement and other detectors are annunciated by zone at the local and main fire detection l- panels.
1.2-24 Clarification: Clarifies the type of automatic fixed extinguishing systems that are actuated by the fire detection system. Other automatic suppression systems have been added that actuate upon detection of heat by fusible link mechanisms integral with sprinkler heads.
l 1.2-24, 25 Correction: Deleted description of plant paging system in relation to detection system. Plant paging system is operated manually per procedures.
1,2-25 Correction: Changes the description of thermal detector types used at CPSES. This change reflects plant conditions.
1.2-25 Correction: Changes the description of the use of strip !
thermistor heat detectors to reflect the as-built plant condition. Spot type thermal detectors are used for transformers not strip thermistors.
1.'2-25 Update: Adds a technical description of flame detectors used in the plant.
1.2-25 Editorial: Deletes description of detection systems which actuate suppression systems. This eliminates redundancy J with description on Page 1.2-24. )
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Attach nt t'o TXX-6848
(;, , October 9, 1987 l Page 2 of<13 L.
FSAR'page. ' Description
'1.2-26 Clarification: Deletes specific statements made regarding "c
alarm system trouble indication to eliminate redundancy.
Alarm system trouble indication is discussed on FSAR Page.
9.5-11.
1.2-26 Clarification: Clarifies the technical descri) tion of i Class A detection that has been provided for tie cable spread room to automatically. actuate the Halon system..
1.2-26 Correction: Changes description of fixed water. spray l- systems to reflect the fact that suppression systems added include water spray,. sprinkler, and Halon systems. !
1.2-26 Correction: Changes the technical description of system o)erating pressures from a specific pressure to reflect t1e changes that occurred during construction..A nonspecific set point is described. The set point will be maintained at a pressure adequate to support suppression systems demands within the plant.
1.2-27 Correction: Changed the description of the number of connections to the underground loop to reflect the
, , addition of connections to meet increased system demands.
l The adequacy of the underground loop connections is !
assured by hydraulic calculations of-system demand. -l 1.2-27 Correction: Deleted description of normally dry l standpipes and deluge valves from the discussion of' :
standpipe isolation. The plant now utilizes normally wet standpipes except in certain highly sensitive areas. The '
adverse effects of these standpipes has been evaluated by the MEB 3-1 criteria and protective measures implemented-where unacceptable interactions were identified. !
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, LAttachment to TXX-6848 3 ' October 9, 1987 Page 3 of 13 FSAR Page Description 1.2-27 Correction: Yard post indicator valves located in the branch lines to the maintenance and administration buildings are used in accordance with NFPA 24, not NFPA 13 and 14.
1.2-27 Correction: Deleted description of water supply and suppression system for the QA record storage area. This storage facility is no longer located in the Administration Building. Fire protection for QA record storage areas in the Administration Building Annex and the CP Engineering Building is provided as stated in FSAR Section 1A(B).
1,2-28 Correction: Extinguishers are adequately 3rovided in the maintenance and administration buildings; lowever, they are not all located in hose stations.
1.2-28 Correction: Changed the technical description of the transformer suppression systems to reflect the as-built design. These systems are actuated automatically by the !
thermal detection system. This improves the response time of the suppression system.
1.2-28 Editorial: Clarifies the description of the type of suppression system, supply independence provided and the description of the water tight door to reflect plant conditions. The technical basis is not affected. )
1.2-28 Correction: Substitutes the hazard that is protected by a deluge system to reflect as-built plant conditions. The diesel generators are protected adequately by an automatic water sprinkler system. 1 i
1.2-28 Correction: Changed the technical description of the l diesel generator day tank suppression systems to reflect )
as-built design. These systems are actuated automatically !
by the thermal detection system. This improves the l response time of the suppression system.
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. Attachment to.TXX-6848 0ctober 9,1987:
Page _4 of 13- <
v y o , ;FSAR Page Description -
cl.2-29' Correction: . Changes'the description of the supply system of fire' protection water'for'the atmospheric cleanup units y outside containment. This change ref.lects plant as-built conditions. Adequate water supply is_ assured'through '
hydraulic calculations.
.I'.2-29 Correction: Changed the description of.the components of the atmos)heric cleanup unit water spray systems to reflect t1e plant as-built conditions. The technical basis is not affected.
1.2-29 Correction: . Changed the technical description of the >
atmospheric cleanup unit suppression systems to reflect the as-built design. These systems are actuated automatically-by the thermal detection system. This-improves the response time of the suppression system.
~1.2-29,.30 Clarification: Deleted details of Halon system since information did not accurately reflect the plant design.
Halon system detailed technical description. appears in Section'9.5.1.4.3.
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- AttachmeritL to' TXX-6848 R , October 9,:1987 I Page 5 of:13 i I
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.FSAR Page- Description 7.4-28 Addition: Adds reference to WCAP-11311,."CPSES Thermal '!
Hydraulic Analysis of Fire Safe Shutdown Scenario"?, and.
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the fire safe shutdown analysis. i p 'FSAR Table ,
Table 7.4-1 Sheets 1 and 3, Table 7.4-3 Sheets 1 and'2-L- Correction: Added a note'to the tables to clarify the' I operational condition of the Train B RHR valve. Switches
., are available for control, but. during normal operation the .!
- valve is not available until the breaker is inserted.
e Table 7.4-1 Sheet.2, Table'7.4-3 Sheet 1 Correction: Added alternate shutdown notation for valve 1-HS-4514. This valve is available.at the hot shutdown panel through.the shutdown transfer panel to isolate Train '
A CCW loop from'the Train B and nonsafeguards loop.
Table 7.4-3 Sheet 1 -i I
Correction:
Added note (A)'to the table.
g Table 7.4-3 Sheet 3 Correction:' Eliminates note (A):from the pressurizer heater. The pressurizer heater is not. required for alternate shutdown.
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, ' Attachment to TXX-6848 October 9, 1987 Page.6 of 13-J' FSAR Page Description
'9.5-3 Clarification: Substitutes a description.of base cur've.
used in determination of. fire protection. Previous reference'was to table derived from the base curve.
Deletts reference to flashover, .a term not descriptive of assumption used.
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i 9.5-4, 5, 6,:22 Clarification: The fire safe shutdown analysis establishes separation'of fire safe shutdown systems or components which may be safety related or non-safety related. 'This change clarifies this= fact.
9.5-4 ' Correction: Added a definition of-Maximum Permissible Fire Loca. The combustible loading calculations have been as-built and this represents'an as-built design limit based on installed. fire' protection features. !
9.5-5 Correction: Changed the assumptions for combustible
-. loading calculations. As-built combustible loading '
calculations have replaced design calculations' originally !
provided. The as-built calculation results have been-reviewed against the Maximum Permissible Fire Load to verify design margin maintenance. The cable loading values are based on cable counts and BTU values'for each cable located in a Fire Area / Zone.
9.5-5 Editorial: Corrects section number for Methodology'to 9.5.1.2.3.
9.5-6 Correction: Changes methodology for calculation of combustible loading. The as-built combustible loading calculations have accounted for the insitu combustibles.
= Transient combustibles are envelnped by the design margin maintained between the as-built coinbustibles and the Maximum Permissible Fire Load.
9.5-7 Clarification: This amendment clarifies in Section 8.b.
that automatic area wide suppression will be installed to protect redundant safe shutdown equipment within'the same fire area when spatial separation is greater than 20 feet when no intervening combustibles of fire hazards exist.
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'F,SAR Page' Description.
- 9.5-7m . Clarification The last paragraph on this page states. 1 that~some areas will'be )rovided with suppression when' case (b) exists. This ciange clarifies?that suppression y' will.be.provided unless justification-of deviation to this'<
condition'is.provided.. .
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'9.5-7~ Update:. Automatic sprinkler suppression system densities are based on_ NFPA 13. The densities stipulated by the.-
, Copper Life Safety. Handbook do not adequately reflect fire hazard configuration and anticipated transient e ,
combustibles which are considered in NFPA 13 hazard
- occupancies.
p 9.5-7 Clarification: Water s) ray is provided for concentrated: ;
cables ~in addition to w1ere area wide s)rinklers are .
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' required. This clarification ensures t1at water spray is R not used as an alternative protection scheme for' condition' l
-(b).unless adequately.. justified.
a 9.5-8 Clarification: This clarification to Paragraph .9 clarifies:when one hour barriers are required. '
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9.5 Clarification
Provides additional clarification on the
, . type of events which initiate ~a trouble alarm and Incorporates' limitations for ground fault supervision.
9.5-12 Clarification: Removes the number three:from the l description of the fire pumps. There are only two fire :
pumps installed in the service water intake structure as described in the preceding paragraph.
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.9.5 Correction: Deletes reference to Factory Mutual Approval of the' pumps and controllers. They have been listed by Underwriters Laboratory for fire protection service. l 9.5-12 Clarification: Adds a' description that reflects the fact some three way hydrants have been used at CPSES. This enhances fire fighting capabilities, i
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' Attachment to'-TXX-6848.,
.0ctober:9, 1987.
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FSAR Page , Description 9.5-12, 13. Correction: Removes reference to brackets which were not utilized in the as-built installation. These brackets as-originally procured, are not necessary for storage.or maintenance of accessories in the hose' cabinets. . Hose wrenches are stored and maintained inside cabinets not 1
, hydrants as stated.
9.5-13 Clarification: Clarifies type of suppression systems utilized in.the as-built installation (i.e., both' i sprinkler and water spray ' systems are employed). The i technical basis is not affected. H 9.5-13 Editorial: Adds a reference to the section of the FSAR that provides a complete technical. description of the !
valve supervision program.
9.5-13 Clarificat ion: Changes the reference for' suppression system spray density criteria to the appropriate FSAR l section. The technical basis is not affected.
9.5-14 Correction: Revises description of deluge valves utilized in water spra units (ACUS)toy reflect systems protecting that atmospheric no provision for manual cleanup operation exists in the as-built installation. The deluge valves provided are for a specialized HVAC application and meet Reg. Guide 1.52 requirements. The valve design precludes inadvertent operation by being seismically qualified. The technical' basis is not affected.
9.5-14 Addition: Add ' reference to plant areas or c >mponents protected by automatic water spray systems to clearly identify where such systems are provided in the as-built installation and to be consistent with other FSAR
' sections. This clarifies'what type of suppression systems are utilized to protect respective plant hazards. The !
technical basis is not affected.
9.5-16 Clarification: Deletes the reference for system spray ;
density criteria. The appropriate FSAR section containing '
this information has been previously identified. The technical basis is not affected, i
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JAttachment$toTXX-684'8
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'Page'9/of,13-FSAR Paget Description
,-9.5-17 Addition: Add' reference'to plant areas protected by manual preaction sprinkler systems to clearly identify where such systems are provided in the as-built' installation and to be consistent with other FSAR sections. This clarifies what type of_ suppression systems are utilized to. protect respective plant hazards. The technica1' basis is not affected.
9.5-17. Clarification: . Deletes the reference to system spray density criteria. The appropriate FSAR.section containing this information has been previously identified. The technical basis is not affected..
9.5-18' Correction: Removes description of Halon local control !
panel locations to reflect as-built plant installation.-
The location described does not' reflect.a code requirement and.may not provide the best design location for all Halon system installations at'CPSES. The technical basis is not' affected.
9.5-18 Addition: Adds reference to the control room and containment building standpipe and hose system being of the normally dry type. design with manual charging required. The normally dry type' design is required to preclude ~the effects of moderate energy line cracks. The technical basis is not affected.
9.5-20 Clarification: Deletes reference to specific suppression systems supplied by yard loop. Specific reference is provided to these. systems in Section 9.5.1.4.2. The technical basis is not affected.
9.5-20 Correction: Changes description'of water tight doors for the diesel generator compartment to reflect the fact that only one doorway requires protection in each compartment.
9.5-21 Clarification: Changes description of water supply for ACU spray systems actuation to a description of water supplies for all suppression systems in plant-safety-related areas. This maintains the consistency of'this section in describing water supplies to all plant and auxiliary buildings. The technical basis is not affected.
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i Attachment to TXX-6848 October 9,'1987 Page 10 of 13 t
FSAR Page Description o 9.5-21 Clarification: Clarifies the technical description of the Halon system. LAdditional detail is added and the system function is restated. The technical basis is not affected.
L' 9.5-22 -Clarification: Clarifies the description-of the detection system to reflect the fact that indicating lamps are not provided for all detectors. This is.not a requirement, l and detection zones affected are thermal type devices I covering smaller areas or of continuous strip type 9.5-23 Correction: Removes description of steel decking since
.this. type of construction is not used at CPSES.
9.5-25' Update: Eliminates exception to provide approved fire dampers with a rating equivalent to that designated for a fire barrier of two hours or greater resistance. Dampers which meet this requirement are being installed.
9.5-26 Revision: Deletes reference to service air powered smoke-ejectors. Adequate smoke removal capacity is available without the services of this type of unit.
~9.5-27 Clarification: Clarifies that steel covers used to i protect vertical cable trays are. installed as a general I construction practice and only extend four (4) feet from the floor where utilized.
9 5-31, 32, Correction: Revises organizational responsibilities to i 33, 34 reflect Nuclear Operations division reorganization. j i
9.5-34 Correction: Revises description _of Engineer to reflect !
the involvement of other Architect Engineers and l consultants in the CPSES project.
- 9.5-37 Clarification: Clarifies the technical description of the fire protectic~ program for the fuel building 3rovided j prior to complete program implementation for t1e plant. I 1
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Page 11of 13 '
[ ' FSAR'Page. _ Description
' 9.5 Correction: Revises' description of personnel responsible for. notification'of'off site fire department assistance.-
Change reflects responsibilities as assigned.at CPSES.
9.5-51; Clarification: Incorporates a technical ' description 'of. ;
fire protection provided for; redundant fire safe shutdown systems within each fire area located inside and outside.
of containment 9.5-54: Correction:. Deletes' technical description o.f metal roof.
deck construction. Roof structures for power. block and~
other safety related ' structures 'are concrete slab.
construction.
( .l L 9.5-54 Correction: Deletes references to' deviations in a noncombustible construction of Wood used to trim the ceiling as h.the control been removed room. ceiling.
as part of' -
a redesign and reinstallation of the' ceiling.
9.5-56 Correction: Changes'the: description of the drainage system for the~ battery rooms to. reflect the fact.that two-battery rooms depend on floor drains -located in an-adjacent corridor. There are no installed suppression systems in these rooms. Any. suppression' water supplied' j would be manual using hose stations.: The doors to these t rooms lwould then be open and the suppression water would drain to the corridor.
9.5-60' Clarification: Changes the description of the code compliance to reflect'the requirements ~of Appendix A to c Branch Technical Position APCSB 9.5-1.
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9.5-70' Clarification: Provides limitations to ground fault ;
supervision. ;
9.5-74 Editorial: Clarifies that pressure maintenance is achieved with one jockey pump.
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' Attachment'to TXX-6848
, October 9,'1987 -
@ .Page 12 of.13 1 1
FSAR Page- : Description
'9.5-95 ' Editorial: Deletes reference to Subsection'9.5.1.3.3 which was deleted from the FSAR by a. previous amendment.
t , 9.5-101' . Edi tori al i- Deletes reference to deviation in Section. j l- 9.5.1.6.2 since the FHA and underlying calculations: 1 L demonstrate compliance with this section. I 9.5-101 ' Addition: Adds description of three hour barriers.between fire areas containing safety related pumps and other. fire areas.
9.5-103, 115 Correction: Provides a discussion on an alternate means of manual . suppression provided for Radwaste Areas. CPSES does not use wheeled extinguishers as suggested in the BTP 9.5-1.
p 9.5-103- Revision: Deletes the provision for large wheeled
>ortable extinguisher units in radwaste' areas. . Adequate 1
, landheld portable extinguishers are provided for the-hazard.
-9.5-106 Editorial: Deletes reference to Section 9.5-1.6.2.G.3 since the CPSES design is described in the text on this page.
9.5-108 Correction: Deletes justification for wood trim used for control room suspended ceiling. The wood trim was removed when the ceiling was redesigned and reinstalled.
9.5-109, 110 Addition: Adds a description of the Bullet Resistant'and Penetration Resistant doors used as fire doors.
Assemblies are similar to units that have been listed with UL by the manufacturer.
9.5-111 Editorial: Clarifies that elevator towers outside 3 containment have a two-hour fire resistance rating. Two two-hour fire barriers would have to be breached to have an affect on safe shutdown.
9.5-115 Correction: Changed capacity of the day tank to reflect as-built plant conditions. The technical basis is not affected. j t
9.5-157, 57, 88,. Update: Deletes Reference 20. Updates Reference 19. i 92, 109, 110, 113 Reference 19 in replaced with a reference containing a complete package of all justifications for deviations.
This reference is the Fire Protection Report - Appendix C
- "Deviations". This also eliminates the need for l Reference 20 throughout the FSAR where deviations are .'
discussed.
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I Attachment to'TXX-6848 '
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October 9, 1987 Page 13 of 13 l FSAR Page Description 9.5-157, 158, 159 Addition: Adds reference to industry standards and applicable editions used for establishing code compliance or as guidance. Change reflects as-built plant-conditions.
Table 9.5-16 Update: Changes made on Page 9.5-8 clearly identify where justification for deviations from area wide suppression and NFPA 13 and 15 are located; therefore, this table is no longer necessary.
Figures 9.5-43,44, 45, 46, 47, and 48 Correction: Replaces existing figures with latest drawing revisions.
010-47 Correction: Updates description of methodology used by CPSES to perform the fire safe shutdown analysis.
010-48 Editorial: Added references to deviations in Section 9.5.1.
010-55 Correction: Changed reference to design documents containing information requested by the NRC. The analysis has been modified to meet current procedural requirements and incorporate plant modifications.
010-63 Clarification: Clarifies that Operator actions are required for fire scenarios other than control room and cable spread room, but the required actions are enveloped i by these scenarios.
010-63 Correction: The Fire Protection Program Review has been revised and is now titled " Fire Safe Shutdown Analysis".
040-144 Correction: Updated response to NRC questions to reflect current analytical techniques used in the analysis for cable separation.
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