|
---|
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
r
==
F9 Log # TXX-88430
=; = File # 10010 clo r C 909.5 7UELECTRIC Ref.#10CFR50.48(e)
April 29, 1988 William G. Counell Eircutin Ykr Presudent U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET N05. 50-445 AND 50-446 FIRE PROTECTION PROGRAM REF: 1) letter logged TXX-6376 f rom W. G. Counsil to the NRC dated April 15, 1987
- 2) Letter . logged TXX-6582 from W. G. Counsil to the NRC dated August 4, 1987
- 3) Letter logged TXX-6728 from W. G. Counsil to the NRC dated October 2, 1987
- 4) Letter logged TXX-6814 from W. G. Counsil to the NRC dated October 22, 1987 Gentlemen:
In the above referenced letters, we have provided you with our revised deviations and comments on SSER 12. The attached list provides comments relating to fire protection cn the SER and additional comments on SSER 12.
The above references along with the attached list identifies areas relating to fire protection of the SER and SSER 12 which may require updating, i Very truly yours, -
W!d4 W. G. Counsil JDS/grr Attachment c - Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3) ,
9 8805030309 800429 5 DR ADOCK 050 dd 400 Nonk Olin Steret LB81 Dekas. Texas 73.'01 l
Attachment to TXX-88430 April 29, 1988 Page 1 of 38 SSER 12 SECTI0ll Page 2-10 DESCRIPTI0tl The control room intakes are equipped with redundant smoke detectors that will isolate the control room in the event of elevated smoke levels.
DISCUSSION Two smoke detectors are located in the control room HVAC intakes, but the detectors are not electrically separated. Additionally, isolation of the Control Room due to elevated smoke levels is accomplished manually.
REFERENCES None
Attachment to TXX-88430 JApril 29, 198E Page 2 of-38 SSER 12 SECTION
-9.5.1,-"Fire Protection", page 9-3 (SSER 12)
DESCRIPTION This section completely supersedes those in previous supplements.
DISCUSSION SSER 12 provides a complete write u) of section 9.5.1 of the SER. However, the statement only -indicates that t1e writeup supersedes writeups in previous supplements to the SER. A clarification of this statement should be provided.
REFERENCES None I
- f i
'-9 9--.--ef yye-e- # WW ym mww-W-7 --Mr- --,rw-rww- mye 7 eg9g-r- w= s 't*--- e y -
w - T rwyu r e-+ w , wM-r-&es-=t--eMw-- w-'-'-=re-
- -+-e+----** -+ --
Attachment to TXX-88430
- April 29, 1988 Page 3 of 38 SSER 12 SECTION 9.5.1.1, page 9-3 and 9-4 DESCRIPTION 9.5.1.1 Fire Protection Program Requirements Fire Protection Program The fire protection program is described in the a)plicant's Fire Protection Evaluation Report and the FSAR. The program esta)lishes policy for the protection of structures, systems, and components important to safety and conforms to the technical requirements in BTP CHEB 9.5-1, Section C.1. The staff finds that the fire protection program meets the guidelines of BTP CMEB 9.5-1, Section C.1, and is,~therefore, acceptable.
Fire Hazards Analysis The applicant's fire hazards analysis enclosed with the letter dated August 15, 1984, identified combustible materials in fire areas, identified safety-related eauipment, determined the consequences of a fire on safe shutdown capability, and summarized available fire protection in accordance with BTP CHEB 9.5-1, Section C.1.b.
DISCUSSION Fire Protection Report and the FSAR discuss the Fire Protection Program.
REFERENCES See letter logged TXX-6814 dated October 22, 1987.
4 e
i
Attachment to TXX-88430 April 29, 1988 Page 4 of 38 1
SSER 12 SECTION 9.5.1.1, page 9-4 DESCRIPTION General Design Criterion (GDC) 3 requires that fire fighting systems be designed to ensure that rupture or inadvertent operation does not significantly impair the safety capability of structures, systems, and components important to safety. To satisfy this requirement, the applicant I has designed components required for hot shutdown so that rupture or inadvertent operation of fire suppression systems will not adversely affect the operability of these components. Where necessary, appropriate protection is provided to prevent impingement of water spray on components required for hot shutdown. Redundant trains of components that are susceptible to damage from water spray are physically separated so that manual fire suppression activities will not adversely affect the operability of components not involved in the postulated fire.
DISCUSSION Hot standby is the design basis for CPSES inadvertent operations evaluation. ,
REFERENCES None ;
1 e
(
e--- , . . - - , .,..--,.---,n, - - , . -,.~n.
Attachment to ThX-88430 April 29,1988 Page 5 of 38 SSER 12 SECT 10tl 9.5.1.1, page 9-4 DESCRIPT10ll On the basis of its review, the staff concludes that the fire hazards analysis meets the guidelines of BTP CMEB 9.5-1, Section C.I.b, and is, therefore, acceptable.
DISCUSS 10fl Fire Protection Report meets the guidance of enclosure 2 of flRC letter dated September 30, 1976.
REFEREflCES FPR Section 11-1.2.1.
~
[ Attachment to TXX-88430 April 29, 1988 Page 6 of 38 SSER 12 SECTION 9.5.1.4, page 9-5 DESCRIPTION All fire-rated assemblies are tested for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> in accordance with American Society for Testing and Materials (ASTM) E 119, are designed in accordance with 3-hour-rated fire barrier designs obtained from the Fire Resistance Directory published by Underwriters Laboratories (UL), or are constructed of 8-inch-thick reinforced concrete in accordance with the "Uniform Building Code" (International Conference of Building Officials) for a minimum fire resistance rating of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
OlSCUSSION 4
UBC design calls for 6 inch thick concrete t>.11s, floors and ceilings.
REFERENCES See letter logged TXX-88309 dated March 11, 1988 from W. G. Counsil to the NRC.
I 4
I l
,_ _ _ . . _ _ _ _ _ _ - _ _ . - - _ . . _ . _ . . _ _ ___,_ ~ - _ .. , ._
Attachment to TXX-88430 April 29, 1988 Page 7 of 38 SSER 12 SECTION 9.5.1.4, page 9-6 DESCRIPTION The heating, ventilation, and air conditioning (HVAC) penetrations of fire-rated barriers are provided with UL-labeled fire damper assemblies that have ratings commensurate with the fire ratings of the walls in which they are installed. The fire dampers are installed according to the manufacturer's directions, with the exception of 61 heating and ventilation dampers identified in the fire hazards analysis on Drawing FHA 2 through FHA 48.
DISCUSSION Essential fire dampers are being replaced with qualified assemblies including deviated openings.
REFERENCES See letter logged TXX-6728 dated October 2,1987. TXX-6728 supercedes comments in TXX-6376.
Attachment to TXX-88430 April 29, 1988 Page 8 of 38 SSER 12 SECTION 9.5.1.4, page 9-7 DESCRIPTION The staff finds that although the watertight and missiie- thd bullet-resistant doors are not 3-hour-fire-rated doors, because of the low to moderate fuel loading and fire protection provided, they provide an equivalent level of protection for the areas where they are installed. On the basis of the above review, the staff concludes that with the acceptable deviation, the fire door provided meet the guidelines in Section C.5.a of BTP CHEB 9.5-1 and are, therefore, acceptable.
DISCUSSION Additional deviations have been identified for Door and Damper Assemblies.
REFERENCES FSAR 9.5.1.6.2 (D.1.j)
- .;t
-Attachment to TXX-88430 April 29, 1988 Page 9 of 38 SSER 12 SECTION 9.5.1.4, page 9-7 DESCRIPTION Thermal insulating materials are noncombustible. Interior walls and structural components, radiation shielding materials, and soundproofing and interior finishes are noncombustible or are listed by a nationally recognized testing laboratory, such as Factory Mutual (FM) or VL, as having a flame spread of 50 or less in their use configuration, with the exception of redwood trim backed with ' fire-retardant-treated pine in the control room. The trim is-a small quantity of wood that constitutes an insignificant contribution to the control room fuel loading. The trim is exposed and visible to personnel continuously manning the control room. Because of the small quantity of wood and its configuration in the control room, the staff finds the installation of
- the redwood trim an acceptable deviation.
DISCUSSION Wood trim has been deleted from the Control Room.
REFERENCES FSAR Amendment 65, Section 9.5.1.6.1 (0.1.d)
?
Attachment to TXX-88430 April 29, 1988 Page 10 of 38 SSER 12 SECTION 9.5.1.4, page 9-7 DESCRIPTION The metal deck roof is constructed of material that is either noncombustible or listed as Class 1 by FM.
DISCUSSION There is no metal deck roofing in safety-related areas of the plant.
REFERENCES FSAR section 9.5.1.6.1.
e
-,r--- r - ,
Attachment to TXX-88430 April 29, 1988 Page 11 of 38 SSER 12 SECTION 9.5.1.4, page 9-8 DESCRIPTION Each oil-filled transformer is protected with a water spray extinguishing system that is automatically actuated by heat detectors. On the basis of its evaluation, the staff concludes that the installation of the transformer meets the guidelines of BIP CMEB 9.5-1, Sections C.5.a(12) and (13), and is, therefore, acceptable.
DISCUSSION A transformer has been added west of the Turbine Building without suppression.
REFERENCES FSAR 9.5.1.4.3, page 9.5-23.
4
Attachment to TXX-88430 April 29,1988 Page 12 of 38 SSER 12 SECTION 9.5.1.4, paragraph 5, pages 9-8 and 9-9.
DESCRIPTION The computer program product is used in conjunction with the safe shutdown logics to identify components that provide a safe shutdown path. After identifying fire-safe-shutdown-related components (i.e., equipment, trays, conduits, and cables) by fire area, the applicant performed an interaction study to locate the fire areas where redundant paths are not properly separated. The interaction study was done by field walkdowns.
DISCUSSION Clarification - the methodology of the study is as given in the Fire Protection Report, Revision 1.
REFERENCES FPR Revision 1, Section 111-4.0 l
l l
l l
l l
l
Attachment to TXX-88430 April 29, 1988 Page 13 of 38 55En 12 SECTION 9.5.1.4, pages 9-9 and 9-10.
DESCRIPTION (1) Service Water Inttke Structure lhe applicant requested a deviation from Section Ill.G.2 of Appendix R (BTP CMEB 9.5-1, Section C.5.b) because complete 1-hour-fire-rated barriers are not providcd to separate the redundant service water pumps.
DISCVSSION Deviation has been revised to include additional components identified in the Fire Safe Shutdown Analysis.
REFERENCES See letter logged TXX-6728 dated October 2, 1987, Deviation la and FPR Revision 1,Section V, Appendix C.
Attachment on TXX-88430 April 29, i,68 Page 14 of 38 SSER 12 SECTION 9.5.1.4, page 9-11.
DESCRIPTION (3) Boric Acid Transfer Pump Area The applicant requested a deviation from Section llI.G.2 of Appendix R (BTPM CHEB 9.5-1, Section C.5.b) because complete 1-hour-fire-rated barriers are not provided to separate the redundant boric acid transfer pumps and complete areawide automatic fire suppression system coverage is not provided.
DISCUSSION Deviation has been deleted.
REJERENCES See letter logged TXX-6728 dated October 2, 1987.
1
Attachment to TXX-88430 April 29, 1988 Page 15 of 38 SSER 12 SECTION 9.5.1.4(4),page9-12 DESCRIPTION The chiller transformer area is located in the auxiliary building on elevation 852 ft. 6 inches. Automatic sprinkler coverage for the area and cable trays, except for the chiller transfonner, is provided. The sprinklers are arranged so that they will not spray directly onto the transformer because the transfonner is sensitive to water. Areawide detection is provided. Cables and associated circuits of one safe shutdown path are enclosed ir. a 1-hour-fire-rated barrier. Manual hose stations and portable fire extinguishers are available.
DISCUSSION Suppression in this area has been upgraded and the deviation has been deleted.
REFERENCES See letter logged TXX-6728 dated October 2,1987.
a
Attachment to TXX-88430 April 29, 1988 Page 16 of 38 SSER 12 SECTI0il 9.5.1.4, page 9-13 DESCRIPTION (5) Hot Shutdown Panel Area Electrical Equipment Room
[ Description of Deviation]
DISCUSSI0fl Fire Hazards Analysis evaluations supersede the deviation.
REFERENCES FPR Revision 1,Section V, Appendix B and letter logged TXX-6728 dated October 2, 1987.
Attachment to TXX-88430 April 29, 1988 Page 17 of 38 SSER 12 SECTION 9.5.1.4, page 9-13 DESCRIPTION (6) Corridor on Elevation 790 ft. 6 in, of the Safeguard Building
[ Description of Deviation]
DISCUSSION Fire Hazard Analysis evaluations supersede the deviation.
REFERENCES FPR Revision 1 Section V, Appendix B and letter logged TXX-6728 dated October 2, 1987.
l l
l 1
Attachment to TXX-88430 April 29, 1988 Page 18 of 38 SSER 12 SECTION 9.5.1.4, page 9-14 DESCRIPTION (7) Valve Isolation Tank Room IC
[DescriptionofDeviation]
DISCUSSION Fire Hazard Analysis evaluations supersede the deviation.
REFERENCES FPR Revision 1,Section V, Appendix B and letter logged TXX-6728 dated October 2, 1987.
1
Attachment to TXX-88430 April 29, 1988 Page 19 of 38 SSER 12 SECT ION 9.5.1.4, Fire Protection of the Safe Shutdown Capability (8), page 9-14.
DESCRIPTION (8) Train A Switchgear Room and Train B Switchgear Room (DescriptionofDeviation]
DISCUSSION Fire Hazards Analysis evaluations supersede the deviation.
REFERENCES See FSAR Section 9.5.1.6.2.F.5, page 9.5-101 See FSAR Section 9.5.1.6.2.D.l.a.2, page 9.5-53 See FPR Section V, Appendix B 6
i l
/
Attachment to TXX-88430 April 29, 1988 Page 20 of 38 SSER 12 SECTION 9.5.1.4 (9), page 9-15 DESCRIPTION (9) Auxiliary Building Heat Exchanger Area (DescriptionofDeviation]
DISCUSSION The Fire Safe Shutdown Analysis assumes that a fire will not induce the failure of mechanical equipment. This deviation is no longer necessary.
REFERENCES FPR Section 111-3.1.3.3.
O
\ r; l :
1
Attachment to TXX-88430 April 29, 1988 Page 21 of 38 SSER 12 SECTION {
9.5.1.4, Fire Protection of the Safe Shutdown Capability (11)
DESCRIPTION (11) Boric Acid Storage Tank Area, Valve Isolation Tank Room 2C, Valve Room 677 hadioactive Penetration Areas, Fire Zones 3A 142 and SB 143, Boron Injection Surge Tank Room, Safeguard Building Elevation 852 ft. 6 in.,
ahd Control Room HVIC Equipment Rooms 73 and 74
[DescriptionofDeviation]
DISCUSSION Fire Hazards Analysis Evaluations supersede this deviation.
REFERENCES See FPR Section V, Appendix 0. See also FPR Section 111 - 3.1.3.3. See also letter logged TXX-6728 dated October 2,1987.
I e
J
Attachment to TXX-88430 April 29, 1988 Page 22 of 38 SSER 12 SECTION 9.5.1, page 9-3 DESCRIPTION The staff has reviewed the fire protection program, as described in the applicant's FSAR through Amendment 55, for confonnance with the Standard Review Plan (SRP, NUREG-0800), Section 9.5.1. This document addresses the applicant's confonnance with Branch Technical Position (BTP) CHER 9.5-1.
DISCUSS 1011 CPSES is committed to Appendix A to APSCB 9.5-1.
REFEREllCES Letter logged TXX-6376 dated April 15, 1987.
Attachment to TXX-88430 April 29, 1988 Page 23 of 38 SSER 12 SECTI0tt 9.5.1.4 (14), page 9-18 DESCRIPT10tl (14) Partial-Sprinkler Protection
[DescriptionofDeviation]
DISCUSS 10fl Fire Hazards Analysis evaluations supersede this deviation.
REFEREllCES See letter logged TXX-6728 dated October 2, 1987. See FPR Section V, Appendix B. See FPR Sections 11-5.1.1.4, 11-5.1.2.4, 11-5.3.1.4, and 11-5.2.1.4.
Attachment to TXX-88430 April 29, 1988 Page 24 of 38 SSE_R 12 SECTIOil 9.5.1.4, page 9-19 1ESCRIPTION (15) Automatic Suppression Systems for Safety Shutdown Capability (Description of Deviation]
DISC _VSSION These systems have been upgraded such that sprinkler head placement is in compliance with NFPA 13. TXX-6728 supersedes these deviations. The Fire Protection Report includes deviations from NFPA codes.
REFEREllCES See letter logged TXX-6728 dated October 2, 1987 and FPR Section 11-6.8.
Attachment to TXX-88430 April 29, 1988 Page 25 of 38 SSER 12 SECTION 9.5.1.4, paragraph 5, page 9-20 DESCRIPTI0fl The applicant's safe shutdown analysis dated May 7, 1982, states that systems needed for hot shutdown and cold shutdown consist of redundant trains and that one of the redundant trains needed for safe shutdown would be free of fire damage by providing separation, fire barriers, and/or alternative shutdown capability.
DISCUSS 10fl The Fire Safe Shutdown Analysis is as given in the Fire Protection Report Revision 1.
REFEREilCES FPR. Revision 1, Section Ill.
Y
\
Attachment to TXX-88430 l Apri,1 29, 1988 !
Page 26 of 38 )
)
SSER 12 SECTION 9.5.1.4, paragraph'2, page 9-21 j DESCRIPTION Reactor decay heat removal for hot shutdown is provided through the steam
. generator by the auxiliary feedwater system and the atmospheric dump valves, and for cold shutdown, by natural circulation, the auxiliary feedwater system, the residual-heat removal system, and the chemical and volume control system charging pumps. These functions can be controlled at the remote shutdown panel.
DISCUSSION For cold shutdown, decay heat removal does not require the Chemical and Volume Control system charging pumps.
REFERENCES FPR,- Revision 1, Section !!I-4.2.
4
l Attacicent to TXX-88430 '
April 29, 1988 Page 27 of 38 SSER 12 SECT!0!i 9.5.1.4, Control of Combustibles DESCRIPT10fl The turbine building does not contain any circuits or eouipment of safe shutdown systems and is separated from such areas by 3-hour-rated fire walls.
DISCUSS 10!i The turbine building contains some fire safe shutdown equipment as identified in the Fire Protection Report.
REFEREflCES See FPR, Section 111-5.0. Also see TXX-6894 and TXX-6376.
T b
Attachment to TXX-88430 April 29, 1988 Page 20 of 38 SSER 12 SECTION 9.5.1.4 Electrical Cable Construction, Cable Trays and Cable Penetrations, page 9-23.
0ESCRIPT10N Small amounts of cable not qualified according to IEEE 383-1974 associated with radiation monitors and security systems are located throughout the )lant.
These cables are all routed in conduit, except for short connectors at t1e detectors. They are low power service cabling.
DISCUSSION Negligible amounts of non-lEEE 383 qualified telephone and radio cable are located throughout the plant as well.
REFERFHCES None 1
Attachment to TXX-88430 April 29, 1988 Page 29 of 38 SSE_R 12 SECTION 9.5.1.4, Lighting and Communications, page 9-24.
DESCRIPTION The applicant has provided a fixed emergency communication system that is independent of the normal plant communication system at preselection stations.
A portable radio communication system has been provided for use by the fire brigade. The portable radio communication system includes hand-held portable radios which are powered by rechargeable batteries. A preoperational test will be conducted to ensure that the frequencies used for portable connunication systems will not affect the actuation of protective relays.
Fixed repeaters are used and they are protected from exposure to fire damage.
The staff concludes that two-way voice communication meets the guidelines of BTP CMEB 9.5-1, Section C.5.g(4), and is, therefore, acceptable.
DISCUSSION Communication is provided via intra plant portable radio, radio talk around capability or page-party /public address system.
REFERENCES See FSAR Section 9.5.1.6.1 0.5.
Attachment to TXX-88430 April 29, 1988 Page 30 of 38 SSER 12 SECTI0li 9.5.1.5, Fire Protection Water Supply System, page 9-25.
DESCRIPTI0ft Fire Protection Water Supply System
[ Description of Fire Water Supply System]
DISCUSS 10tl The fire protection water supply has been modified and has a new water service and pumping system.
REFEREllCES See FSAR Section 9.5.1.4.2.20, 9.5.1.4.3, 9.5.1.6.1 (E.2.c, d, e, and f) and FPR Section 11-6.3.2 and 6.3.3.
- Attachment to TXX-88430 April 29, 1988 Page 31 of 38 SSER 12 SECTION 9.5.1.5, Sprinkler and Standpipe Systems, page 9-27 DESCRIPTION Sprinkler and Standpipe Systems (Description of Deviation]
DISCUSSION Differences from NFPA codes are given in the Fire Protection Report.
REFERENCES See FPR Section 11-6.8.
T i
Attachment to TXX-88430 April 29, 1988 Page 32 of 38 SSER 12 SECTION 9.5.1.6, Diesel Fuel Oil Day Tank Rooms OESCRIPTION The day tanks can hold 2,300 gallons of diesel fuel instead of the maximum of 1,100 gallons recommended by the guidelines. Because each 2,300-gal...
DISCUSSION Diesel Day tanks hold 2160 gallons of diesel fuel.
REFERENCES See FSAR Section 9.5.1.6.1 and 9.5.1.6.2 (F.9) m am
Attachment to TXX-88430 April 29, 1988 Page 33 of 38 SSER 12 SECTION ,
9.5.1.7, Summary of Deviations from BTP APCSB 9.5-1 DESCRIPT10ft (3) no dampers installed in HVAC penetrations of 3-hour-fire-rated barriers (Section 9.4.1.4)
DISCUSSION Qualified fire dampers have been installed. Deviation has been deleted.
REFEREllCES See letter logged TXX-6728 dated October 2, 1987.
i
}
i j
Attachment to TXX-88430 April 29, 1988 Page 34 of 38 SSER 12 SECTION 9.5.1.7, Summary of Deviations from BTP CHEB 9.5-1, page 9-31.
DESCRIPTION (c) boric acid transfer pump area (DescriptionofDeviation]
DISCUSSION Deviation has been deleted.
REFERENCES See letter logged TXX-6728 dated October 2, 1987.
a
Attachment to TXX-88430 April 29, 1988 '
Page 35 of 38 i
SSER 12 SECTION 9.5.1.7, Summary of Deviations from BTP CNEB 9.5-1, page 9-31.
DESCRIPTION (6) partial-sprinkler coverage in 20 plant areas (Section 9.5.1.4).
a) chiller transformer area b) hot shutdown panel area c) corridor elevation 790 ft. 6 in. safeguard building room 71a d valve isolation tank room IC ,
fe)) valve isolation tank room fire area SB2C f auxiliary building fire area AA g auxiliary building 790-ft elevation fire zone 21a i h auxiliary building 810-ft elevation fire zone 21b ,
i auxiliary building fire area AA fire zone 21c j) auxiliary building 830-ft elevation fire zone 21d '
k) auxiliary building 852-ft elevation fire zone 21f 1 electrical and control building fire area EA m electrical and control building elevation 778 ft. fire area EA43 n safeguard building fire area SA o) safeguard building fire area SB ,
safeguard building elevation 810 ft. 6 in, fire zone SB8 ,
1 safeguard building elevation 831 ft. 8 in, fire zone 5815 boric acid transformer pump area s) train A switchgear room (t) train B switchgear room ;
DISCUSSION Fire Hazards Analysis Evaluations have superseded these deviations see comment.
REFERENCES See letter logged TXX-6728 dated October 2, 1987. ;
4 i
L t
Attachment to TXX-88430 April 29, 1988 Page 36 of 38 SSER 12 SECTION 9.5.1.7, Summary of Deviations from BTP CHED 9.5-1, page 9-31.
DESCRIPil0N (a) auxiliary building heat exchanger area i DISCUSS 10H r
The Fire Safe Shutdown Analysis does not postulate that a fire could disable ;
mechanical components such as heat exchangers. !
REFERENCES See FPR Section 111 3.1.3.3.
I 4il l
l 1'
i
- . - , ~ - _ - - -
.,. - , - _ - - , , _ _ _ _ _ _ _ _ , , - ,-_y_, __-.._,, -- - --_-- --__,_.-_- o
Attachment to TXX-88430 April 29, 1988 Page 37 of 38 SSER 12 SECTION 9.5.1.7, Summary of Deviations from B1P CMEB 9.5-1, page 9-31.
DESCRIPTION (9) omission of automatic fire suppression system in eight plant areas (Section 9.5.1.4):
boric acid storage tank area a
b valve isolation tank room 2C c valve room 67 d) radioactive penetration areas fire zones SA 142 and SB 143 e) boron injection surge tank room safeguard building elevation 652 ft.
6 in.
(f) control room HVAC equipment rooms 73 and 74.
DISCUSSION A Fire Hazards Analysis supercedes these deviations.
REFERENCES See letter logged TXX-6728 dated October 2,1987.
l i
I
Attachment to TXX-88430 April 29, 1988 Page 38 of 38 SSER 12 SECTION
, 9.5.1.7, Summary of Deviations from BTP CHEB 9.5-1, page 9-32 DESCRIPTION (10) installation of automatic sprinklers not in accordance with NFPA 13 in 10 plant areas (Section 9.5.1.4):
(a) auxiliary building 790-ft. elevation fire area AA fire zone 21e (b) auxiliary building 810-f t. elevation fire area AA fire zone 21b (c) auxiliary building 831-ft elevation fire area AA fire zone 21d d) auxiliary building 854-f t, elevation fire area AA fire zone 21f e) safeguard building 790-ft. elevation fire area 50 fire zone 4 f) safeguard building 810-ft, elevation fire area SB fire zone 8 (g) safeguard building 831-ft. elevation fire area SB fire zone 15 (h) safeguard building 831-ft. elevation fire area SB fire zone 144 (i) electrical and control building 792-ft. elevation fire area EA fire zone 57 (j) electrical and control building 792-ft. elevation fire area EA fire zone 43.
0_1SCUSS10N These systems have been upgraded such that sprinkler head spacing is in compliance with NFPA 13. NFPA code deviations are supersed these deviations. Code deviations are now given in the fire Protection Report.
R_EFERENCES See FPR Section 11-6.8.
.