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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 TXX-9026, Forwards Addendum to Unit 1 Preservice Insp (PSI) Summary Rept, Providing Remaining Info & Editorial Corrections Re PSI & Addressing Exams & Tests of Code Class 1 & 2 Sys as Stipulated in PSI Plan1990-08-13013 August 1990 Forwards Addendum to Unit 1 Preservice Insp (PSI) Summary Rept, Providing Remaining Info & Editorial Corrections Re PSI & Addressing Exams & Tests of Code Class 1 & 2 Sys as Stipulated in PSI Plan 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 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 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 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 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 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 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 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 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 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 ML20042F3051990-05-0202 May 1990 Provides Revised Response to Generic Ltr 88-17 Re Loss of DHR 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) 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. ML20012D0151990-03-19019 March 1990 Responds to NRC 900216 Ltr Re Violation a Noted in Insp Repts 50-445/90-03 & 50-446/90-03.Corrective Actions: Groundwater Calculations Completed & Engineering Personnel Reminded of Procedural Requirements 1990-09-04
[Table view] |
Text
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- -- Log # TXX-89595 r, L- 2 File # 10010 E 3 L
Ref # 10CFR20.106 n! ELECTRIC August 25, 1989-U..S. Nuclear. Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 TRANSMITTAL OF 0FFSITE DOSE CALCULATION-MANUAL (ODCM). REV. 1 REF:- (1) TU Electric letter (TXX-89118) to NRC dated Maren 2, 1989 (2) TU Elect'ric letter (TXX-89226) to NRC dated April 28, 1989 Gentlemen:
Enclosed is Revision 1 of the CPSES Offsite Dose Calculation Manual (ODCM).
Revision 0 of the ODCM was submitted to the NRC for review in March, 1989 (reference 1). Revision 1 ir.corporates editorial corrections as well as changes to ODCM requirements and calculational methodologies that are
. considered technical in nature.
i In Revisior. 1, those technical' changes-and editorial changes that could potentially be considered substantive are identified by.a Revision.bar in the margin next to the change. Pages with. Revision bars and certain pages of the
~
Table.of. Contents are identified with.a "Rev. 1, 8/89" notation at the bottom.
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Otherwise, the Rev. O, 3/89 notation is. maintained. In order to assure that the enclosed copy of the 0DCM is complete, a list of effective pages is attached. This listing identifies each effective page and indicates whether it is a Rev. O page 11.e., an original page) or if it has been changed in Revision 1 of the document. This list should be inserted in the ODCM binder.
A description of the technical changes and the editorial changes that could l potentially be considered substantive. together with their justification and an indication of SER/SSER' impact, is included as an attachment in this transmittal' package. Also included with each description and justification is L the Group' identifier, as discussed in reference 2.
1 Although the final CPSES Te:hnical Specifications have not been issued, the requirements of draft Technical Specification. Administrative Control 6.14, regarding enanges to the ODCM, were followed for this revision. Additionally, it is to be noted that these changes have been discussed with Wayne Meinke of the NRC staff.
10 @
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.(.3909D h D l
'PD8 400 N. Olive Dallas. Texas 75201 b
E____________
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TXX-89595 August 25, 1989 Page 2 of 2 i
(
TV Electric requests that the NRC perform an expedited review of this material i and inform us as to its acceptability. If you have any questions, please !
contact either Doug Kay or Ray Ashley of the TU Electric staff.
l Sincerely, j l
I
/ ,
l William J. Cahill, Jr. ?
RLA/smp Enclosures {
Attachments c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) l 1
f* 'Att'achment L, .
" TXX-89595- CPSES ODCM REVIS20N 1 H**4 .
DETAILED DESCRIPTION Page=1 v; . 3
)0DCM.Page.
fas amended) Grcup Description'
'- xiii 3 JAdds a statement' referring to a new Appendix 6 containing addttional' guidance regarding the implementation of certain ODCM requirements.
Correction:
This change adds information to aid in implementation of the requirements being addressed.
SER/SSER Impact: No
~
I 3/4-8, 22 4 See Page No(s):II 1-16 and II 2-14 Substitutes " Radiological Effluent Control" or. i
" Control" for " Specification" or " Technical Specification".
Clarification:
This' change is made to complete the transfer of the Radiological Effluent Technical Specifications to the ODCM.
SER/SSER Impact: No I 3/4-24 4 Adds a footnote to Table 4.11-2 to explain the analysis frequency of the Plant Vent noble gas monitor.
Clarification:
This change reflects ine fact that the noble gas concentration in the Plant Vent is analyzed.
' continuously by a radiation monitor.
Related SER'Section: 11.2.2 SER/SSER Impact: No I 2/4-36 3 Changes an entry in the column " Type and Frequency of Analysis" in the Radiological Environmental Monitoring
, Program, relating to the type of sample to be used for analyzing drinking water in the waterborne pathway.
Correction:
This change to a composite sample is made to achieve consistency with the required sampling type for this source.
SER/SSER Impact: No I 3/4-37 3 Modifies the requirement for the sampling of broad leaf vegetation grown nearest each of the two different offsite locations of highest predicted ground level D/0 under certain conditions.
Revision:
These changes (i.e., from three different kinds of broad ieaf vegetation to a single sample, and from
" monthly" to " monthly, when available") are made since only limited types of broad leaf vegetation are found in the CPSES environs during the spring and early
[
" ttachmnt CPSES ODCM REVISION ^1 '
l 'TXXe89595 . DETAILED DESCRIPTION' Pag 2.2' l 1
ODCM'Page-(as amended) Group Description summer months.
'SER/SSER Impact: No l
I 3/4-37 3 Adds a footnote for the Food Product Pathway. sampling program. j Revision: .
This change-is made to compensate'for the reduction in 3" the sampling requirements for broad leaf vegetation as specified in the Standard Radiological Effluent-Controls. (This revision to the program will mair,tain ;
the overall effectiveness of the Radiological Environmental Monitoring Program.) .
SER/SSER Impact: No I 3/4-38 4 Deletes the parenthetical portion of the text in Note (2) for Table 3.12-1. j Editarial: )
This change is made because the deleted inaterial pdded confusion: furthermore, this material was provided as guidance in the Standard Radiological Effluent Controls and was, in fact, considered in the development of this ODCH. ! q l- SER/SSER Impact: No a I 3/4-44 3 Adds missing text to Action Stateme9t 'b', for Control 1 3/4.12.2, " Land Use Census'",
Correction:
This text is added since it was inadysrtently omitted during the preparation of the Rev. O document. (The wording is taken from the Standard Radiological Effluent Controls.) ,
SER/3SER Impact: No a
I 6-3 3 ' Modifies the approval requirements for changes to the ODCM.
Revision:
This change is made to be consistent with the Administrative Control Requirements of Technical 4 Specification 6.14 (Rev. F). )
Related SER Section: 13.1.1.2 '
SER/SSER Impact: No i
I 6-3 3 Substitutes " Technical Specification" for " Control" in <
Section 6.9.1.4.
Correction:
This change is made to note that the action statenents .,
for liquid holdup tanks and gas storage tanks are in {
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_ _ _ - _ _ - - _ - _ _ - - - _ _ _ - - _ .- - - - - - - _ - - - - - 1
~Attachm:nt 'CPSES ODCM REVISION'l-l- .TXX.-89595 DETAILED DESCRIPTION. Page 3
.c 1>
1 00CM Page c 1 1133-amended) Sr_9#R Description the Technical Specificatiert.
} SER/SSER Impact: No I.B 3/'-6 3 Replaces the last sentence in the text describing the bases for Control 3/4.11.2.2, " Dose - Noble Gases".
Addition:
This change, concerning the proportioning of releases-among units sharing radwaste treatment systems, is made to be consistent with the bases for Controls 3/4.12.2.2 and'3/4.12.2.4. (The revised wording is consistent with the Standard Radiological Effluent Controls.)
SER/3SER Impact: No
!)'1 2 Changes the list of system pumps that are available'to discharge liquids to the circulating water discharge fahal.
Correction:
These changes are wade to be consistent with the as--
hu; ?t Liquid Matts Management Lyttera pumps available for liqu'd 6f4cnarge.
Related SER Section: 11.2.1
~SER/SSER Impact: Wo II 1-3, 4 3 Revises Sections 1.1.2 and 1.1.4, which describe tee ,
effluent flow rate used in the calculat$on of the ~
dilution facter fcr.all liquid radwaste system b:tch discharges.
Revision:
This change is made to reflect the modification'of radiation monitor XRE-5253 (to off-line vs. in line services which elitninated a built-in safety factor in the calculational methodology. ,(As compensation, a safety factor of 2 hat been apelied in the methodo?ogy for ca'culating the required dilution factors in Section 1.1.5 of Part II; see page II 1-4a.)
SER/SSER Impact: No II 1-4 3 Adds information to Sections 1.1.3 and 1.1.4 which describes corrections that can be made to the dilution j flow in order to allow for simultaneous releases.
Addition:
This change is made to the calculational methodology to provide an additional consideration that can be utilized in the determination of liquid effluent concentrations and alarm setpoints. (The revised methodology corrects the available dilution flow for a release by subtracting the required dilution flow for l any other concurrent release. This method will l l
I
Attach:;nt CPSES ODCM REVISION 1-l 9: ?
- TXX.-89595' DETAILED DESCRIPTION- 'Paga 4 l
10DCN Page
, lag _apg_nded) Group DescrintJAn I . i
- ' continue to assure compliance with 10 CFR 20.)
Related SER Section: 11.2.1 SER/SSER Impact: No L II 1-4. 4a 3 Modifies the methodology for calculating the Required l- Dilution Factor by applying a. safety factor of 2.
Correction:
This change is made to ccupensate for the loss of the safety factor which resulted from relocation of detecter X2E-5253 to off-liue service.(see Detailed Description for.0DCM Page 11 1-3 and -4).
SER/SSER Impact: No II 1-17 !? Adds 6 footnote referring to Supplemental Guidance Statement #3 which states thet discharge to the Low Level Retention pond may continue if tritium is' d.eter.ted and the cource of the tritium can bc traced to '
t5e TG Primery Water Cooling System (TGPWCS). 4
. Add-1ti on :
This change is &&de tu incorporate the guidance provided by Supplemental Guidance Statenent #3.
SER/SSER Impact: Ph) 11 2-16 3 Adds the Dose Factors for Kr-83m to Table 2.1.
Corruction:
This change is made because this isotope was . .
inadvertently omitted during preparation of the Rev. O document. (The specific dose factor valuet were obtained from Table B-1 Of Reg. Guide 1.109. Rev. 1.)
SER/SSER-Impact: No j II 2-50. 55 3 fiodifies the definition of tne f.er' ins "D sub o" and "1500".
Correction: )
These changus make the definitions consistent with what is used in other parts of the ODCM.
SER/SSER ImpPct: No II 2-55 3 Modifies the definition of the term "3000". ,
Correction:
This change is made to being the definition into con-formance with Radiological Effluent Control 3.11.2.1 which limits the dose rate due to noble gases to 500 mrem /yr whole body and 3000 mrem /yr to the skin. I SER/SSER Impact: No
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Attach:2nt
,. TXF-89595 CPSES ODCM-REVISION 1 DETAILED DESCRIPTION Page 5 00CM Page
~(as amended) Group Description II-C 4 Adds information to the definition of the term a describing.the~ ground plane dose conversion factor.
Clarification:
This change is made to clarify that the doses associated with the ground plane exposure pathway ar'e applicable to all organs even though only total body and skin dose conversion factors are provided.- (The added wording is taken from Reg. Guide 1.109. Rev. 1.)-
SER/SSER Impact::No II G-1 5 Supplemental Guidance Statement #1 provides guidance pertaining to acceptable means for complying with the LLD for the grab. samples required by Action Statements 31 and 32 of Radiological Effluent Control 3/4.3.3.4.
Addition:
This guidance clarifies the methodology for achieving compliance by specifying the cpplicable LLD values to be used in analysis of the required grab samples.
SER/SSER Impact: No 11 G-2 2 Supplemental Guidance Statement #2 provides information regarding application of the required LLD to be used in implementing the analysis of the monthly Batch Waste Release Tank sample as required by Tab 1'e 4.11-1.
Addition:
This guidance statement indicctes that this LLD value applies to the noble gas isotopes listed in Notation 2 of Table 4.11-2.
SER/SSER Impact: No II G-3, 4 & 5 3 Supplemental Guidance Statement #3 indicates that when tritium is detected in the Turbine Building (TB) sumps and it is known that this tritium is due to leakage from the TG Primary Water Cooling System (TGPWCS),
discharge to the Low Level Retention Pond may continue.
Addition:
This guidance statement recognizes that the TB sump sampling requirements, in accordance with Table 4.11-1, are based on primary to secondary leakage whereas the tritium in the TGPWCS is a known, fixed quantity. (In support of this. supplemental guidance, an accompanying analysis is provided which demonstrates that release of the er. tire tritium content from the TGPWCS would result only in a negligibly small dose.)
SER/SSEE tmpact: No II G-6 3 Supplemental Guidance Statement #4 adds an alternate means far implementing the CCW Drain Tank sampling and L ____ _
Attach :nt CPSES ODCM REVISION 1
[ . .~ T
- TXL-89595- DETAILED DESCRIPTION Page 6.
l -dll)[
rODCM Page (as amended) lAtn a- Descriot' ion analysis requirement of Table 4.11-1.
Addition:
This guidance statement recognizes that the discharge of liquid from the CCW Drain Tank can be accomplished by routing it to the Waste Mater Holdup Tank and per-forming the required batch sampling prior to discharge of that tank. (This is required because'all inputs to the CCW Drain Tank cannot be isolated for batch dis-charges.)
SER/SSER' Impact: No i
t.
~
COMANCHE PEAK STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL List of Effective Pages l
EPL-i August, 1989 1
l l
I l CPSES - ODCM List of Effective Pages Preface The Effective Page Listing (EPL) provides a tabulation of the effective pages in the CPSES ODCM.
Each page in the CPSES ODCM is identified with a page number, including pages that contain tables or figures.
A revision number and date are included on each page. If the page is revised but the revision is not considered substantive (i.e., it is an editorial correctior.), the revisfon number will not be changed. The revision number and date are changed when the change represents a substantive revision to the information that is provided on the page. If a page, or portion thereof, is reprinted without any change, neither the new revision number nor the new revision date will be added to that page; rather, the existing amendment number and date will be maintained.
Since the EPL is not updated with each revision, an Instruction Sheet (s) will be provided for subsequent revisions of the CPSES ODCM; it should be retained immediately in front of the EPL. To identify the effective revision level of a page in the CPSES ODCM, check these Instruction Sheets first and, if not found, the EPL second.
If any effective page cannot be found, notify TU Electric Nuclear Licensing and the required effective pages will be provided. Contact may be made by phone (214/812-4358) or by mail. A marked up copy of pages from the Instruction Sheets or the EPL is a convenient way to identify the required pages.
I 1
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l EPL-ii August, 1989 l
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CPSES ODCM Effective Page 1.isting PART I
./aae No. Revision Not i 1 11 1 iii 0 iv 1 v 1 vi 0 vii 0 viii 0 1x 0 x 0 xi 1 xii 0 xiii 1 1 1-0 0 1 1-1 0 1 1-2 0 1 1-3 0 1 1-4 0 1 1-5 0 1 1-6 0 1 2-0 1 1 3/4-0 0 I 3/4-1 0 1 3/4-2 0 1 3/4-3 0 ,
I 3/4-4 0 j I 3/4-5 0 '
I 3/4-6 0 I 3/4-7 0 I 3/4-8 1 I 3/4-9 0 I 3/4-10 0 l
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, 7: , ::< ..
- r. ,
L CPSES ODCM
. Effective Page. Listing j i
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~ l Pace-No. Revision No. j i
I 3M-11 ~0 -l I'3/4-12 0 l I 3/4-13 0' ;
I 3/4-14 0 -i I 3/4-15' O {
I 3/4-16 0~ l I 3/4-17 0-
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i I 3/4 0 I 3/4-19 0 I 3/4-20. -0 ;
I 3/4-21 0 !
.I 3/4 22 1 j l I 3/4-23 0 <l I.3/4-24 1 l
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! 3/4-26 0 I 3/4-27 .0- j I 3/4-28 0 '!
'I 3/4-29 0- {
.I 3/4-30 0' ;
I'3/4-31 0 .j I 3/4-32 O ;
I 3/4-33 0 'l
'I 3/4-34. 0 .j I 3/4-35 0 {
I 3/4-36-(rev. bar was inadvertently omitted) 1 I 3/4-37 (rev. bar was inadvertently omitted) 1 I 3/4-38 (rev..bar was inadvertently omitted) 1 l I 3/4-39 0 l I 3/4-40 0 I 3/4-41 0 l I 3/4-42 (rev. bar should be deleted) 0 1 1 3/4-43 0 l I.3/4-44 1 1 3/4-45 0 i
l EPL I-2 August, 1989
CPSES ODCH Effective Page Listing PART I Pace No. Revision No.
I B 3/4-0 1 I B 3/4-1 0 I B 3/4-2 0 I B 3/4-3 0 I B 3/4-4 0 I B 3/4-5 0 I B 3/4-6 1 I B 3/4-7 0 I B 3/4-8 0 I B 3/4-9 0 I B 3/4-10 0 I B 3/4-11 0 1 5-0 (no revision no. & no date)
I 5-1 0 1 5-2 0 I 6-0 (no revisior, no. & no date)
I 6-1 0 1 6-2 0 I 6-3 1 1 6-4 0
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EPL I-3 August, 1989
i . s:- .
CPSES ODCM Effective Page Listing PART II Pace No. Revisfon_Mo.1 II 1-1 0 11 1-2 1 II 1-3 1 II 1-4 1 II 1-4a 1 II 1-5 0 II 1-6 0 II 1-7 0 II 1-8 0 II 1-9 0 11 1-10 0 II 1-11 0 II 1-12 0 11-1-13 0 II 1-14 0 11 1-15 0 II 1-16 1 II 1-17 1 II 1-18 0 II 1-19 0 II 1-20 0 II 1-21 0 II 1-22 0 II 1-23 0 II 1-24 0 I'i 1-25 0 1J 2-1 0 II 2-2 0 II 2-3 0 II 2-4 0 11 2-5 0 II 2-6 0 II 2-7 0 II 2-8 0 II 2-9 0 EPL 11-1 August, 1989
CPSES ODCM Effective Page Listing PART II Pace No. Revision No.
II 2-10 0 II 2-11 0 II 2-12 0 II 2-13 0 II 2-14 1 II 2-15 0 II 2-16 1 II 2-17 0 11 2-1B 0 II 2-19 0 II 2-20 0 II 2-21 0 II 2-22 0 II 2-23 0 II 2-24 0 II 2-25 0 II 2-26 0 II 2-27 0 II 2-28 0 II 2-29 0 II 2-30 0 II 2-31 0 II 2-32 0 II 2-33 0 II 2-34 0 II 2-35 0 II 2-36 0 II 2-37 0 II 2-38 0 II 2-39 0 II 2-40 0 II 2-41 0 II 2-42 0 II 2-43 0 II 2-44 0 II 2-45 0 1
EPL II-2 August, 1989 L_______
CPSES ODCM Effective Page Listing PART II Pace No. Revision No.
II 2-46 0 11 2-47 0 II 2-48 0 II 2-49 0 II 2-50 1 II 2-51 0 II 2-52 0 II 2-53 0 II 2-54 0 II 2-55 1 11 2-56 0 II 2-57 0 11 2-58 0 II 2-59 0 11 2-60 0 II 3-1 0 11 3-2 0 II 3-3 0 II 3-4 0 II 3-5 0 II 3-6 0 II 3-7 0 II 3-8 0 II 3-9 0 II A-1 0 II B-1 0 i
II C-1 1 II D-1 0 II D-2 0 II E-1 0 II E-2 0 II F-1 0 II F-2 0 1
i EPL II-3 August, 1989 e '
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- Effective Page Listing PART II Pace No. . Revision No.
G-0 1 G-1 1 G-2 1 G-3 1 G-4 1 G-5 1 G-6 1 l
EPL II-4 August, 1989
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