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Category:CORRESPONDENCE-LETTERS
MONTHYEARTXX-9924, Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span1999-10-22022 October 1999 Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span ML20217M5711999-10-20020 October 1999 Forwards Insp Repts 50-445/99-15 & 50-446/99-15 on 990822- 1002.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy TXX-9923, Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred1999-10-15015 October 1999 Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred ML20217E7951999-10-12012 October 1999 Forwards COLR for Unit 1,Cycle 8,per TS 5.6.5 ML20212L2891999-10-0101 October 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals. Purpose of GL Was to Obtain Info That Would Enable NRC to Verify That Condition of Licensee SG Internals Comply with Current Licensing Bases TXX-9922, Forwards Revised COLR, for Cycle 5 for Unit 21999-10-0101 October 1999 Forwards Revised COLR, for Cycle 5 for Unit 2 ML20216J5571999-10-0101 October 1999 Provides Final Response to GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps ML20212G0721999-09-24024 September 1999 Forwards Rev 4 to Augmented Inservice Insp Plan for CPSES, Unit 1. Future Changes & Revs to Unit 1 Augmented Inservice Insp Plan Will Be Available on Site ML20212H0461999-09-24024 September 1999 Forwards Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 990820 ML20212F7481999-09-24024 September 1999 Forwards SER Authorizing Relief from Exam Requirement of 1986 Edition ASME Code,Section XI Pursuant to 10CFR50.55a(a)(3)(ii) for Relief Request A-3 & 10CFR50.55a(g)(6)(i) for Relief Requests B15,16,17 & C-4 ML20212F1041999-09-23023 September 1999 Requests That NRC Be Informed of Any Changes in Scope of Y2K System Deficiencies Listed or Util Projected Completion Schedule for Comanche Peak Steam Electric Station,Units 1 & 2 ML20212E6661999-09-21021 September 1999 Advises That Info Contained in Application & Affidavit, (CAW-99-1342) Re WCAP-15009,Rev 0, Comache Peak Unit 1 Evaluation for Tube Vibration Induced Fatigue, Will Be Withheld from Public Disclosure ML20212D9111999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of CPSES & Did Not Identify Any Areas in Which Performance Warranted Insp Beyond Core Insp Program.Core Insp Plan at Facility Over Next 7 Months.Insp Plan Through March 2000 Encl ML20212A7601999-09-14014 September 1999 Forwards Insp Repts 50-445/99-14 & 50-446/99-14 on 990707-0821.Four Violations Occurred & Being Treated as Ncvs.Conduct of Activities Was Generally Characterized by safety-conscious Operations & Sound Radiological Controls TXX-9921, Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC1999-09-10010 September 1999 Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC ML20211P3761999-09-0707 September 1999 Ack Receipt of Ltr Dtd 990615,transmitting Rev 30 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20211L9871999-09-0303 September 1999 Forwards Rev 31 to Technical Requirements Manual. All Changes Applicable to Plants Have Been Reviewed Under Util 10CFR50.59 Process & Found Not to Include Any USQs TXX-9915, Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl1999-09-0303 September 1999 Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl ML20211K2231999-08-31031 August 1999 Forwards Txu Electric Comments of Rvid,Version 2 ML20211J3801999-08-27027 August 1999 Forwards Corrected TS Page 3.8-26 to Amend 66 to Licenses NPF-87 & NPF-89,respectively.Footnote on TS Page 3.8-26 Incorrectly Deleted ML20211G7301999-08-26026 August 1999 Forwards Revs 29 & 30 to CPSES Technical Requirements Manual (Trm). Attachments 1 & 2 Contain Description of Changes for Revs 29 & 30 Respectively ML20211G1081999-08-26026 August 1999 Responds to NRR Staff RAI Re Util Mar 1999 Submittal for NRC Review & Approval of Changes to CPSES Emergency Classification Procedure ML20211G3441999-08-25025 August 1999 Forwards Response to NRC RAI on LAR 98-010 for Cpses,Units 1 & 2.Communication Contains No New Licensing Commitments Re Cpses,Units 1 & 2 ML20211B2861999-08-18018 August 1999 Forwards Insp Repts 50-445/99-13 & 50-446/99-13 on 990720- 23.No Violations Noted.Insp Included Implementation of Licensee Emergency Plan & Procedures During Util Biennial Emergency Preparedness Exercise ML20211C4661999-08-18018 August 1999 Discusses Proprietary Info Re Thermo-Lag.NRC Treated Bisco Test Rept 748-105 as Proprietary & Withheld It from Public Disclosure,Iaw 10CFR2.790 ML20210U3981999-08-17017 August 1999 Forwards Monthly Operating Repts for July 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs or SVs for Plant Occurred ML20211C0991999-08-17017 August 1999 Forwards Rev 3 to ASME Section XI ISI Program Plan,Unit 2 - 1st Interval, Replacing Rev 2 in Entirety ML20211C4571999-08-16016 August 1999 Forwards Omitted Subj Page of Contractor TER TXX-9919, Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 9908021999-08-16016 August 1999 Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 990802 ML20210R6561999-08-13013 August 1999 Forwards Response to NRR 990805 Telcon RAI Re License Amend Request 98-010,to Increase Power for Operation of CPSES Unit 2 to 3445 Mwth & Incorporating Addl Changes Into Units 1 & 2 TS ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210S6411999-08-12012 August 1999 Informs That Wg Guldemond,License SOP-43780,is No Longer Performing Licensed Duties.Discontinuation of License Is Requested ML20210R2221999-08-12012 August 1999 Forwards Insp Repts 50-445/99-10 & 50-446/99-10 on 990510-0628.Violations Noted & Being Treated as Ncvs, Consistent with App C of Enforcement Policy ML20210N1101999-08-0404 August 1999 Provides Supplemental Info to Util 990623 License Amend Request 99-005 Re Bypassing DG Trips.Info Replaces Info Contained in Subject Submittal in Attachment 2,Section II, Description of TS Change Request ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210J2301999-08-0202 August 1999 Forwards Amend 96 to CPSES Ufsar.Replacement of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,Rev 2 ML20210J6071999-08-0202 August 1999 Forwards line-by-line Descriptions of Changes in Amend 96 to CPSES UFSAR Transmitted by Util Ltr TXX-99166,dtd 990802. Replacment of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,rev 2 TXX-9916, Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 9907271999-08-0202 August 1999 Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 990727 TXX-9918, Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-9906301999-08-0202 August 1999 Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20210K2321999-07-29029 July 1999 Forwards Insp Repts 50-445/99-12 & 50-446/99-12 on 990530-0710.No Violations Noted ML20210G5861999-07-29029 July 1999 Forwards fitness-for-duty Program Performance Data for Six Month Period of Jan-June 1999 ML20210J0121999-07-27027 July 1999 Forwards Summary of Methodology for Determination of NDE Measurement Uncertainty,In Response to Recent Discussions with NRC Re LAR 98-006 Concerning Rev to SG Tube Plugging Criteria TXX-9917, Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES1999-07-26026 July 1999 Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES ML20210F3121999-07-26026 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, ML20210D8231999-07-23023 July 1999 Forwards Safety Evaluation of Relief Requests Re Use of 1998 Edition of Subsections IWE & Iwl of ASME Code for Containment Insp ML20210D3211999-07-21021 July 1999 Provides List of Estimates of Licensing Actions,In Response to Administrative Ltr 99-02,dtd 990603 ML20210C2931999-07-21021 July 1999 Supplements 880323 Response to NRC Bulletin 88-02, Rapidly Propagating...Sg Tubes, Non-proprietary WCAP-15010 & Proprietary Rev 0 to WCAP-15009, CP Unit 1 Evaluation for Tube Vibration... Encl.Proprietary Rept Withheld ML20209H0111999-07-16016 July 1999 Forwards Relief Request C-4 to CPSES Unit 2 ISI Program for Approval ML20210C3331999-07-16016 July 1999 Forwards Exam Repts 50-445/99-301 & 50-446/99-301 on 990618- 24.Exam Included Evaluation of Six Applicants for Senior Operator Licenses ML20209H2551999-07-16016 July 1999 Forwards ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2 & Containment ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2,per ASME Boiler & Pressure Vessel Code,Section Xi,Paragraph IWA-6230 1999-09-07
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARTXX-9924, Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span1999-10-22022 October 1999 Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span TXX-9923, Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred1999-10-15015 October 1999 Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred ML20217E7951999-10-12012 October 1999 Forwards COLR for Unit 1,Cycle 8,per TS 5.6.5 ML20216J5571999-10-0101 October 1999 Provides Final Response to GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps TXX-9922, Forwards Revised COLR, for Cycle 5 for Unit 21999-10-0101 October 1999 Forwards Revised COLR, for Cycle 5 for Unit 2 ML20212G0721999-09-24024 September 1999 Forwards Rev 4 to Augmented Inservice Insp Plan for CPSES, Unit 1. Future Changes & Revs to Unit 1 Augmented Inservice Insp Plan Will Be Available on Site ML20212H0461999-09-24024 September 1999 Forwards Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 990820 TXX-9921, Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC1999-09-10010 September 1999 Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC ML20211L9871999-09-0303 September 1999 Forwards Rev 31 to Technical Requirements Manual. All Changes Applicable to Plants Have Been Reviewed Under Util 10CFR50.59 Process & Found Not to Include Any USQs TXX-9915, Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl1999-09-0303 September 1999 Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl ML20211K2231999-08-31031 August 1999 Forwards Txu Electric Comments of Rvid,Version 2 ML20211G1081999-08-26026 August 1999 Responds to NRR Staff RAI Re Util Mar 1999 Submittal for NRC Review & Approval of Changes to CPSES Emergency Classification Procedure ML20211G7301999-08-26026 August 1999 Forwards Revs 29 & 30 to CPSES Technical Requirements Manual (Trm). Attachments 1 & 2 Contain Description of Changes for Revs 29 & 30 Respectively ML20211G3441999-08-25025 August 1999 Forwards Response to NRC RAI on LAR 98-010 for Cpses,Units 1 & 2.Communication Contains No New Licensing Commitments Re Cpses,Units 1 & 2 ML20210U3981999-08-17017 August 1999 Forwards Monthly Operating Repts for July 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs or SVs for Plant Occurred ML20211C0991999-08-17017 August 1999 Forwards Rev 3 to ASME Section XI ISI Program Plan,Unit 2 - 1st Interval, Replacing Rev 2 in Entirety TXX-9919, Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 9908021999-08-16016 August 1999 Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 990802 ML20210R6561999-08-13013 August 1999 Forwards Response to NRR 990805 Telcon RAI Re License Amend Request 98-010,to Increase Power for Operation of CPSES Unit 2 to 3445 Mwth & Incorporating Addl Changes Into Units 1 & 2 TS ML20210S6411999-08-12012 August 1999 Informs That Wg Guldemond,License SOP-43780,is No Longer Performing Licensed Duties.Discontinuation of License Is Requested ML20210N1101999-08-0404 August 1999 Provides Supplemental Info to Util 990623 License Amend Request 99-005 Re Bypassing DG Trips.Info Replaces Info Contained in Subject Submittal in Attachment 2,Section II, Description of TS Change Request TXX-9918, Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-9906301999-08-0202 August 1999 Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20210J2301999-08-0202 August 1999 Forwards Amend 96 to CPSES Ufsar.Replacement of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,Rev 2 ML20210J6071999-08-0202 August 1999 Forwards line-by-line Descriptions of Changes in Amend 96 to CPSES UFSAR Transmitted by Util Ltr TXX-99166,dtd 990802. Replacment of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,rev 2 TXX-9916, Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 9907271999-08-0202 August 1999 Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 990727 ML20210G5861999-07-29029 July 1999 Forwards fitness-for-duty Program Performance Data for Six Month Period of Jan-June 1999 ML20210J0121999-07-27027 July 1999 Forwards Summary of Methodology for Determination of NDE Measurement Uncertainty,In Response to Recent Discussions with NRC Re LAR 98-006 Concerning Rev to SG Tube Plugging Criteria TXX-9917, Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES1999-07-26026 July 1999 Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES ML20210F3121999-07-26026 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, ML20210C2931999-07-21021 July 1999 Supplements 880323 Response to NRC Bulletin 88-02, Rapidly Propagating...Sg Tubes, Non-proprietary WCAP-15010 & Proprietary Rev 0 to WCAP-15009, CP Unit 1 Evaluation for Tube Vibration... Encl.Proprietary Rept Withheld ML20210D3211999-07-21021 July 1999 Provides List of Estimates of Licensing Actions,In Response to Administrative Ltr 99-02,dtd 990603 ML20209H2551999-07-16016 July 1999 Forwards ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2 & Containment ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2,per ASME Boiler & Pressure Vessel Code,Section Xi,Paragraph IWA-6230 ML20209H0111999-07-16016 July 1999 Forwards Relief Request C-4 to CPSES Unit 2 ISI Program for Approval ML20209G0721999-07-13013 July 1999 Forwards Monthly Operating Repts for June 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs of SV Occurred During Reporting Period ML20209F0681999-07-0909 July 1999 Informs That Effective 990514,TU Electric Formally Changed Name to Txu Electric.Change All Refs of TU Electric to Txu Electric on Correspondence Distribution Lists ML20209E0421999-07-0909 July 1999 Forwards Response to NRC Request for Addl Info on LAR 98-010.Attachment 1 Is Affidavit for Info Supporting LAR 98-010 ML20209B6021999-06-30030 June 1999 Submits Second Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Readiness Disclosure for Reporting Status of Facility Y2K Readiness Encl ML20195J6981999-06-15015 June 1999 Provides Addl Info Related to Open Issue,Discussed in 990610 Conference Call with D Jaffe Re ISI Program Relief Request L-1 Submitted by Util on 980220 ML20196A4921999-06-15015 June 1999 Forwards Rev 30 to Physical Security Plan.Rev Withheld,Per 10CFR73.21 ML20195J0491999-06-14014 June 1999 Submits Response to RAI Re Implementation of 1.0 Volt Repair Criteria ML20195J0651999-06-14014 June 1999 Submits Response to RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves 05000445/LER-1999-001, Forwards LER 99-001-00, Some Electrical Contacts for RCS Pressure Relief Valves Were Not Included in Surveillance Testing Procedures. New Licensing Commitments Identified in Attachment 11999-06-0808 June 1999 Forwards LER 99-001-00, Some Electrical Contacts for RCS Pressure Relief Valves Were Not Included in Surveillance Testing Procedures. New Licensing Commitments Identified in Attachment 1 ML20195F0091999-06-0808 June 1999 Forwards Response to RAI Re Units 1 & 2 ISI Program for Relief Requests E-1 & L-1.Communication Contains No New Licensing Basis Commitments Re Cpses,Units 1 & 2 ML20207E1921999-05-28028 May 1999 Submits Updated Request for NRC Staff to Review & Approve Certain Changes to CPSES Emergency Plan Submitted in 981015 & s Prior to Changes Being Implemented at CPSES ML20207E1711999-05-28028 May 1999 Supplements 990526 LAR 99-004 as TU Electric Believes Extingency Exists in That Proposed Amend Was Result of NOED Granted to Prevent Shudown of CPSES Unit 1 ML20207D9841999-05-26026 May 1999 Requests That NRC Exercise Enforcement Discretion to Allow Cpses,Unit 1 to Remain in Mode 1,power Operation,Without Having Performed Svc Test,Per SR 4.8.2.1d on Unit 1 Battery BT1ED2 ML20195B6351999-05-25025 May 1999 Submits Response to RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves TXX-9912, Forwards Txu Electric (Formerly TU Electric) CPSES Emergency Preparedness Exercise Scenario Manual for 990721-22,Graded Exercise1999-05-21021 May 1999 Forwards Txu Electric (Formerly TU Electric) CPSES Emergency Preparedness Exercise Scenario Manual for 990721-22,Graded Exercise ML20206U1981999-05-20020 May 1999 Forwards Form 10K Annual Rept,Per 10CFR50.71(b). Communication Contains No New Licensing Basis Commitments Re Cpses,Units 1 & 2 ML20196L1931999-05-20020 May 1999 Forwards MOR for Apr 1999 for Cpses,Units 1 & 2.During Reporting Period There Have Been No Failures or Challenges to Power Operated Relief Valves or Safety Valves TXX-9911, Forwards non-proprietary & Proprietary Responses to RAI Re LAR 98-010 by Incorporating Attached Changes Into CPSES Unit 2 OL NPF-89 & CPSES Units 1,OL NPF-87 & 2 TS to Increase Licensed Power.W & Caldon Proprietary Responses Withheld1999-05-14014 May 1999 Forwards non-proprietary & Proprietary Responses to RAI Re LAR 98-010 by Incorporating Attached Changes Into CPSES Unit 2 OL NPF-89 & CPSES Units 1,OL NPF-87 & 2 TS to Increase Licensed Power.W & Caldon Proprietary Responses Withheld 1999-09-03
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059K6141990-09-17017 September 1990 Submits Documentation of 900906 Telcon Re Addl Util Candidate for Licensed Operator Generic Fundamentals Exam Section ML20059G8761990-09-10010 September 1990 Forwards Rev 8 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML20059F8461990-09-0404 September 1990 Responds to NRC Re Violations Noted in Insp Repts 50-445/90-22 & 50-446/90-22 on 900606-0705.Corrective action:OPT-467A Changed to Provide Addl Prerequisite Info Re Solid State Protection Sys Switch Lineup During Testing ML20059E4981990-08-31031 August 1990 Forwards Revised Radial Peaking Factor Limit Rept for Cycle 1 Per Tech Specs Through Amend 1 & ML20059E4201990-08-30030 August 1990 Forwards Objectives & Guidelines for 1990 Emergency Preparedness Exercise Scheduled for 901113 ML20028G8281990-08-29029 August 1990 Forwards Comanche Peak Unit 1 Semiannual Radioactive Effluent Release Rept,900403-0630 & ODCM TXX-9030, Forwards Endorsements 40 & 4 to Nelia Policy NF-274 & Maelu Policy M-90,respectively & Endorsements 10,11,12,13,14 & 15 to Maelu Policy MF-1311990-08-27027 August 1990 Forwards Endorsements 40 & 4 to Nelia Policy NF-274 & Maelu Policy M-90,respectively & Endorsements 10,11,12,13,14 & 15 to Maelu Policy MF-131 ML20059F4381990-08-23023 August 1990 Forwards Public Version of Revised Emergency Plan & Corporate Emergency Response Procedures,Consisting of Rev 1 to EPP-313,Rev 7 to CERP-101,Rev 7 to CERP-102 & Revised Forms.W/Dh Grimsley 900906 Release Memo TXX-9029, Responds to NRC Re Violations Noted in Insp Repts 50-445/89-57 & 50-446/89-57.Corrective Actions:Storage Facilities for Instrumentation & Control Work Packages Improved to Provide Acceptable Protection for Documents1990-08-20020 August 1990 Responds to NRC Re Violations Noted in Insp Repts 50-445/89-57 & 50-446/89-57.Corrective Actions:Storage Facilities for Instrumentation & Control Work Packages Improved to Provide Acceptable Protection for Documents ML20058P0571990-08-13013 August 1990 Forwards, Comanche Peak Steam Electric Station Unit 1 Control Room Simulator 10CFR55 Certification Initial Rept ML20058N2311990-08-0909 August 1990 Forwards First Half 1990 fitness-for-duty Program Performance Data,Per 10CFR26.71(d).Point of Contact for Personnel,Random Testing Program Results & Confirmed Positive Tests Summary & Mgt Summary Included in Data ML20059A5831990-08-0404 August 1990 Responds to Info Request Made During 900802 Meeting Re Inadvertent Safety Injections on 900726 & 30 & Results of 100% Power Plateau Testing TXX-9024, Provides Status of Exam Activity & Revised Completion Schedule for Portion of Exam.Util Deferred Preoperational Testing of Facility Spent Fuel Pool Cooling & Cleanup Sys Until Prior to First Off Loading of Spent Fuel1990-08-0303 August 1990 Provides Status of Exam Activity & Revised Completion Schedule for Portion of Exam.Util Deferred Preoperational Testing of Facility Spent Fuel Pool Cooling & Cleanup Sys Until Prior to First Off Loading of Spent Fuel TXX-9022, Forwards Detailed Descriptions of Changes in Amend 79 to FSAR for Comanche Peak Steam Electric Station1990-07-31031 July 1990 Forwards Detailed Descriptions of Changes in Amend 79 to FSAR for Comanche Peak Steam Electric Station TXX-9027, Responds to NRC Re Violations Noted in Insp Repts 50-445/90-19 & 50-446/90-19.Corrective Action:Specific Activity within Tech Spec Limits.No Further Corrective Action Required1990-07-30030 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-445/90-19 & 50-446/90-19.Corrective Action:Specific Activity within Tech Spec Limits.No Further Corrective Action Required ML20055J1571990-07-27027 July 1990 Submits Info Re Replacement of Borg-Warner/Intl Pump,Inc Check Valve Swing Arms,Per .Swing Arms in ASME Code Class 2 Check Valves Will Be Replaced During First Refueling Outage ML20056A0461990-07-24024 July 1990 Requests Regional Waiver of Compliance for Containment Pressure Transmitter 1-PT-934 During Coming Outage TXX-9023, Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. No Subj Transmitters in Existence at Facility1990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. No Subj Transmitters in Existence at Facility ML20055G6351990-07-17017 July 1990 Submits Results of Remote Shutdown Panel Environ Survey ML20055F9391990-07-13013 July 1990 Advises That Operators Have Gained Significant Experience in Operating Plant Under Wide Range of Conditions & Have Demonstrated Necessary Proficiency to Safely Operate Unit ML20055F9371990-07-13013 July 1990 Submits Info Re Revised Acceptance Criteria for THERMO-LAG Fire Barrier,Per 900705 Telcon.On Exposure to Heat Flux at Surface of Barrier,Listed Mechanisms Activated.Fire Testing Demonstrates That Panels Qualified W/Variation in Thickness ML20044A7001990-06-26026 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Util Will Implement for Unit 2 Activities Performed for Unit 1 ML20044A1411990-06-20020 June 1990 Forwards Endorsements 4 & 5 to Nelia Certificate N-90, Endorsements 5 & 6 to Maelu Certificate M-90 & Endorsements 34,35,36,37,38 & 39 to Nelia Policy NF-274 ML20043H7031990-06-18018 June 1990 Discusses Mod/Rework to Auxiliary Feedwater Sys Check Valves Mfg by Bw/Ip Intl,Inc.All But One Affected Check Valve modified.Motor-driven Auxiliary Feedwater Pump Discharge Valve Check Valve Body Replaced ML20043H2181990-06-15015 June 1990 Forwards Response to 900515 Request for Addl Info on Emergency Preparedness.Ongoing Emergency Preparedness Programs Address Concerns Raised by Citizens for Fair Util Regulation ML20043G3131990-06-15015 June 1990 Forwards Addl Info Re Pressurizer Surge Line Thermal Stratification & leak-before-break Evaluation & Nonproprietary Suppl 3 to WCAP-12247, Supplementary Assessment... & Proprietary Suppl 3 to WCAP-12248 ML20043C5671990-06-0101 June 1990 Discusses Identification of Slave Relays Tested Using Alternative Methodology,Per 900402 Commitment.Encl Tabulation Identifies Test Type,Applicable Procedures & Equipment & Impact of Improper Documentation ML20043E7131990-06-0101 June 1990 Responds to NRC 900517 Notice of Violation & Imposition of Civil Penalty in Amount of $25,000.Corrective Action:Qc Mgt Counseled Level III Inspector & QC Supervisor on Importance of Good Communications W/Receipt Inspectors ML20043C4501990-05-31031 May 1990 Advises That Util Revised FSAR Section 15.1.2 & Question/ Response 32.108,per 10CFR50.59 ML20043B5471990-05-25025 May 1990 Provides Status of Facility Design & Const Activities,Per Request.Detailed Design Work Will Resume in June 1990.Const Activities Expected to Increase Signficantly by Jan 1991 ML20043B5481990-05-23023 May 1990 Provides Clarification of 890710 Commitment Re Power Ascension Program.Cooldown Portion of Remote Shutdown Test Performed During Preoperational Testing,Per FSAR & Reg Guide 1.68.2 ML20043D1711990-05-21021 May 1990 Forwards Public Version of Revised Emergency Plan Procedures,Including Rev 8 to EPP-109,Rev 7 to EPP-112,Rev 4 to EPP-116 & Rev 6 to EPP-121.W/DH Grimsley 900604 Release Memo TXX-9018, Advises of Completion of Implementation of Requirements of Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety- Related Equipment1990-05-21021 May 1990 Advises of Completion of Implementation of Requirements of Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety- Related Equipment ML20043B0981990-05-15015 May 1990 Forwards Radial Peaking Factor Limit Rept for Cycle 1, Containing F(Xy) Limits for All Core Planes Containing Bank D Control Rods & All Unrodded Core Planes ML20042F2851990-05-0303 May 1990 Supplemental Response to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. ML20042F3861990-05-0303 May 1990 Responds to NRC 900410 Ltr Re Violations Noted in Insp Repts 50-445/90-10 & 50-446/90-10 on 900206-07 & 0226-0302. Corrective Action:Memo Issued Emphasizing That Discrepancies Should Be Brought to Attention of Site Organizations ML20042F3021990-05-0202 May 1990 Responds to NRC 900402 Ltr Re Violations Noted in Insp Repts 50-445/89-23 & 50-446/89-23.Util Does Not Believe That Circumstances Described in 900402 Ltr Constitutes Violation of 10CFR50.9(a) ML20042F3051990-05-0202 May 1990 Provides Revised Response to Generic Ltr 88-17 Re Loss of DHR ML20042E4581990-04-12012 April 1990 Responds to Inconsistencies in Terminology & Labelling Identified During NRC 890118 & 19 Audit of Facility Dcrdr. Util Believes Control Room Inventory Requirement of Suppl 1 to NUREG-0737,satisfied ML20042E0701990-04-10010 April 1990 Discusses 900305 Meeting W/Nrc in Rockville,Md Re Offsite Power Availability for Automatic Switch Co Solenoids for MSIV in Event of Nonmechanistic Main Steam Line Crack in Superpipe Region ML20012F5011990-04-0303 April 1990 Forwards Corrections to 891016 Response to Emergency Diesel Generator Engine Requirements.Lengths of Two Pairs of Bolts Above Crankpin Shall Be Measured Ultrasonically Before Detensioning & Disassembly of Bolts ML20012F3221990-04-0202 April 1990 Discusses ESF Sys Slave Relay Alternate Test Methodology. Implementation Schedule for Design Mods to Relay Will Be Submitted by 900601 ML20042D8081990-03-29029 March 1990 Forwards Proposed Change to FSAR Section 13.4 Re Station Operations Review Committee.Similar Change Submitted in 900328 Ltr for Chapter 6 of Facility Tech Specs ML20012F0411990-03-28028 March 1990 Forwards marked-up Pages of Facility Draft Tech Specs & Bases (NUREG-1381) Provided W/Low Power OL ML20012E6051990-03-27027 March 1990 Forwards Endorsements 1-4 to Maelu Certificate M-90, Endorsements 1-9 to Maelu Policy MF-131,Endorsements 29-33 to Nelia Policy NF-274 & Endorsements 1-3 to Nelia Certificate N-90 ML20012E6531990-03-27027 March 1990 Provides Final Response to Reporting Requirement 2 of NRC Bulletin 88-008, Thermal Stresses in Piping Connected to RCS, for Unit.Nde Requirements of Action 2 Not Considered Applicable to Unit ML20012E1911990-03-23023 March 1990 Forwards Comanche Peak Steam Electric Station Unit 1 Cycle 1 Startup Physics Tests Control Rod Worth Predictions Utilizing TU Electric Control Rod Swap Methodology. ML20012E1581990-03-23023 March 1990 Clarifies 880624 Response to NRC Generic Ltr 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants. ML20012D0201990-03-19019 March 1990 Advises That Allegations Provided to NRC by Former Util Employee Unsubstantiated,Based on Investigation by Util Safeteam Organization ML20012E2181990-03-19019 March 1990 Responds to Generic Ltr 89-19 Re USI A-47, Safety Implication of Control Sys in LWR Nuclear Power Plants. Util Determined That Loss of safety-related Inverters 1 or 2 Would Involve Coincidental Opening of Main Feedwater Valves 1990-09-04
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TEXAS UTil.lTIES GENERATING COMinNY ' Log # TXX-3411 , ,
=>umvas uno:n su.am- m.ii File # 913 y .v auv a cymcws September 29, 1981 Mr. Harold R. Llenton, Director 41 Office of Nuclear Reactor Regulation Y U. S. Nuclear Regulatory Commission Washington, D.C. 20555 g[l([ f[fV >
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SUBJECT:
COMANCHE PEAK STUG ELECTRIC STATION DOCKET i40S. 50 445 ANb 50-446 hi s
bjQ.h Q#
DOCUMENTATION OF ITEMS DISCt)SSED DURING SEPTEMBER 2 - 4, 1981 AUDIT TEAM VISIT
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5 '
Dear Mr. Denton:
On September 2 - 4, 1981 an NRC audit team visited our of fices to explore items of concern and to confirm staff findings as stated in the Comanche Peak SER with respact to organiidtignal structure and qualifications. Enclosed is documentation of certain items discussed during this visit.
Please let us know if you require any additional information on this matter.
\
Sincereiy, _
.L/ l D >"
BRC: tis Enclosures ,
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8110060294 810929^ '
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\,- Enclosure to TXX-3411
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$V, b 1.A.},2 Shift Supervisor Administrative' Duties a ,
,w s A list of administrative duties bf the' Shift Supervisor will be
, provided to the Vice President, Nuclear, for review prior to fuel load. ' Administrative functions that detrac: from or are subordinate to the management responsibility for ensuring the safe operation of the plant shall be delegated to other operations personnel with no control room operating duties. I Auxiliary Operators and clerical pusonnel will assume these functions.
1.A.1.3 Shift Manning A Shift Technical Advisor (during Modes 1, 2, 3 & 4), a Communicator (member of the Shift Operating Organization), and two Radiation Protection Tephnicians (one qualified to initiate the post-accident sampDng 67,d u.alysis process) will be assigned to each shift.
3 .
Restrictions on the use of overtime, previously discussed in ODA-302,
" Relief of Perso.1nel and Overtime Restrictions", are now incorporated A, ' in Procedure STAsbl5, " Staff Work Hours", a copy of which is attached
\,4, for your review. - +
y.m 1.C.2 Shift Relief My Turid/pr Procedures s (
The checksheet for Auxiliary Operators, as discussed in ODA-302,
" Relief of Personnel", has not been completely developed. However, the precursor to that checklist, " Operator Guidelines", is attached for your review. .
A.
1.C.5 Procedures for Fhedback of Operating Experience to Plant Staff The Operations.hpport Superintendent is responsible for dissemination of all. pert'nent operating experience infonnatioa received from industry cources.5 2ncluded is the INP0 information received from the
. SEE-IP. program which,is disseminated per procedure NOA-XXX (to be
' numbered later).. Other procedures will be developed to handle other es/ 50urces ofMnformation such as NRC bulletins and orders, NRC information notices, and'tne many other sources of industry operating experience information. Procedures will also be developed which ensure that N operating experiences reported onsite, including all licenses event s reports are reviewed by operations support section personnel (STA's)
_ and routed to the appropriate departments including the training department.
13.1.2.1 Plant Staff One operator with at least one year of PWR operating experience will be available on each shift until the plant reaches the maximum licensed power level.
13.4.3 Independent Safety Engineering Group The Independent Safety Engineering Group (ISEG) reporting to the Operations Support Engineer will consist of five engineers with experience in the areas of electrical, mechanical, and nuclear engineering. The Operations Support Engineer, Mr. M. J. Riggs',
resume is attached. At this time, no individuals have been hired to fi el positions as ISEG members. We are proceeding imediately to staff the ISEG with the most qualified individuals available. We will cequire a minimum of three years engineering experience for all individuals at the time they are assigned to the ISEG and will imediately involve them in the design, construction, preoperational testing and initial startup of CPSES to maximize their nuclear power plant experience. This program will ensure that when the ISEG is fully implemented 90 days prior to fuel load, the ISEG members are qualified to carry out their responsibility to improve the overall quality and safety of operations.
TMI-2 Requirements 1.A.1.1. Shift Technical Advisor The Operations Support Engin'eer will provide Shift Technical Advisors to each operating shift in support of the shift supervisor. These Shift Technical Advisors (STAS) will meet the education, experience and training requirements of NUREG-0737, October 31, 1980, Appendix C
" Nuclear Power Plant Shift Technical Advisor". Staffing of these positions began in the Spring of 1981. Presently, there are four Shift Technical Advisors at CPSES. Their resumes are attached.
This initial group of STAS will begin training in October,1981. This training will be conducted by Westinghouse Electric Corporation and by CPSES training personnel and exceeds the requirements of NUREG-0737.
Other groups of STAS will attend similar training programs prior to fuel load of Unit 1.
The necGsary experience required for STAS by NUREG-0737 will be gained by involving these personnel in preoperational and startup testing activities and in design and construction engineering activities at CPSES. At the time of initial fuel load of Unit 1, the necessary number of qualified STAS will be availabic to support the operation of CPSES.
e Operating experience information that is internally generated will be renorted as directed in Procedure ODA-107, " Reporting of Operational Incidents", a copy of which is attached. This report will then be routed to appropriate personnel for their review in accordance with ODA-106, " Review of Documents", a copy of which has been previously transmitted.
The Operations Engineer is responsible for maintaining thorough familiarity with daily station operating activities (ODA-101,
" Operations Department Organization and Responsbilities", Sections 4.2.1, 4.2.2 and 4.2.6, attached). This daily contact with shift operating personnel and Operation Department staff meetings that occur approximately weekly are the primary vehicles for oral dissemination of important information that is not routed as directed in ODA-106.
O Michae1. J. Riggs - Operations' Support Enginecr Education:
i B.S. Nucle.ar Engineering - Texas A&M University - May 1974 General Electric Company Field Engineering Development ; enter, Schenectady, New York - June - October 1974 Large S;eam Curbine Generator Course (6 weeks)
Boiling Water Reactor Technology Course (6 weeks)
General Electric Boiling Heter Reactor Train Center, Morris, Illicois - April - July 1975 Reactor Operator Certification Course (12 weeks)
Instructor Training Course (2 weeks)
Irperience:
Octohar 1974 - April 1975:
Employed by General Electric Company assigned to Brunswick Steam Electric Plant startup group for initial training. Assisted in Rad-waste systems construction and startup. Prsoperationally tested several Radwaste processing systems and seismic monitoring systems.
Assistant G.E. Operational Shift Supervisor for Reactor Initial Operation Testing.
July 1975 - January 1976:
Employed by General Electric Compant, assigned to General 31ectric BWR Training Center as instructor. Taught utility company operators BWR operations and control of all BWR systems. Developed material and lesson plans for specific BWR plant training courses and for GE nee instructors internal training course.
Februarv 1976 - Junc 1978:
Employed by General Electric Company assigned to E. I. Hatch Nuclear Generating Plant startup group. Wrote large percentage of Plant Operating Procedures, including: systems operation instruction, emer-l gency procedures, calibration and maintenance procedures, functional
! and surveillance testing procedures and annunciator response procedures.
l Wrote and reviewed Preoperational Test Procedures. Reviewed Reactor i Startup Test Instructions. Assigned as Preoperational Test Supervisor for Reactor Protection System, Primary Containment Isolation System and Main Generator and Auxiliary Systems; responsible for those system's assembly, deficiencies, construction, acceptance testing, functional testing, preoperational test / testing and support documents. GE Operations Shift Supervisor for Reactor Vessel Hydro and for Recire Pump Vibration Testing. Training Instructor for GE Shift Supervisor Certification course.
. . _ . _ . - . . _ _ . _ , , - _ _ . _ _ . _ _ _ . . . . . ~ _ _ _ . _ , . . . _ . _ , . _ , _ _ . _ , _ _ - _ . _ , _ - _ _ , _
. o O
Michael J. Riggs - Page 2 June 1978 - December 1980:
Employed by Texas Utilities Generating Company assigned to Comanche Peak Steam Electric Station startup group. - Initiated Hydraulic Mbdel
! Test Plan for Containment Recirculation Sump flow verifications. Assign-ed es Startup Test Engineer for station battery /DC distribution systems and for all main turbine and generator systems. As turbine / generator coordinator, responsibilities included construction and startup schedul-ing, installation verification and system testing.
January 1981 - September 1981:
Employed by Texas Utilities Generating Company assigned as Electrical Prerequisite Test Coordinator responsible for technical di.rection of startup test electricians, electrical support manpower assignments and projections and develepoent cf backlog testing to include most plant 6.CK7 large motors.
October 1, 1981:
- Employed by TUGC0 in the pcsition of Operati
- ans' Support Engineer responsible for Shift Technical Advisors and for Independent Safety l Engineering Group.
Certifications:
GE Senior Reactor Operator Certification on Dresden Station Units 2 & 3 -
July 1975 GE Senior Reactor Operator Certification on E.I. Hatch Plant Units 1 & 2 - May 1978 Professional Affiliations:
None l
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SHIFT TECHNICAL ADVISOR RESUMES J. B. McINVALE - Shift Technical Advisor Education:
B.S.N.E. - Georgia Inst':ute of Technology -1981 Experience:
1981 - Employed by the Texas Utilities d"en'erating Company as Engineer (Operations Support).
W. L. STENDEBACH - Shift Technical Advisor Educacion:
B.S.N.E. - Texas A&M University - 1981 Experience:
1980 - Employed by Central Power and Light Company at the Barney 11.
Davis Power Plant as a maintenance helper.
1980 - Employed by Texas A&M University at the Radiological Safety Office engaged in radiation surveying and radioactive waste management.
1981 - Employed by the Texas Utilities Generating Company as Shift Technical Advisor m _
. ~
SHIFT TECHNICAL ADVISOR RESUMES Page 2 M. W. SUNSERI - Shift Technical Advisor Education:
B.S.N.E. - Texas A&M University - 1981 Experience:
1981 - Employed by the Texas Utilities Generating Company as Shift Technical alvisor.
M. D. PALMER - Shift Technical Advisor Educatica:
l B.S.M.E. - Texas Technological University - 1981 1
Experience:
1978 - Employed by Standard Oil of Indiana as engineering trainee.
1979 - Employed by Texas Electric Service Company at Morgan Creek Steam Electric Station.
1981 - Employed by Texas Utilities Generating Company at Comanche Peak Steam Electric Station.
i
COMANCHE PEAK STEAM ELECTRIC STATION STATION ADMINISTRATION MANUAL i
1i w!L Vi Lv STAFF WORK HOURS PROCEDURE NO. STA - 615 BEVISION No. 0 SUBMITTED BY: DATE:
Administrative Supervisor APPROVED BY: DATE:
Menager, Plant Operations l
CPSES ISSUE DATE PROCEDURE NO.
STATION ADMINISTRATION !!ANUA1. STA-615 STAFF WORK HOURS REVISION NO. O PAGE 2 0F 3 1.0 Purpose The purpose of this procedure is to establish a sound policy covering working hours for plant staff who perform safety related functions.
2.0 Applicability This procedure applies to plant staff who perform safety related functions (e.g., senior reactor operators, reactor operators, health physicists, auxiliary operators, 1 & C Technicians,; key maintenance personnel, etc.). This procedure becomes effective when determined '
appropriate by the Manager, Plant Operations.
3.0 Definitions ~
None 4.0 Instructions
. 4.1 Overtime Limitations 4.1.1 Overtise shall not be routinely scheduled to compensate for an inadequate number. of personnel te meet the shif t .
erew staffing requirements. ilowever, du> to unanticipated
" 'or unavoidable circumstances, personnel say be required to work overtime to comply with the shif t crew staffing requirements. in the event that overtime must ce used (excluding extended periods of shutdown for refueling, major maintenance or major plant modifications), che following overtime limitations for plant staff performing safety related functions shall be followed:
4.1.1.1 An individual shall not be permitted to work more than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> straight.
Note: This limitation does not include shift
, turnover time.
4.1.1.2 There shall be a break of at least 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (which can include shift turnover time) between all work periods.
4.1.1.3 An individual shall not work more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7 day period.
4.1.1.4 An individual should not be required to work more than 14 consccutive days without having 2 consecutive days off.
- I
CPSES ISSUE DATE PROCEDURE NO.
STATION ADMINISTRATION MANUAL STA-615 STAFF WORK HOURS REVISION NO. O PAGE 3 0F 3 4.1.2 Deviations from-these limitations may be authorized by the Manager, Plant Operations, his designee, or.a higher level of management. The cause for any such deviation shall be documented.
4.1.3 If a licensed operator or senior licensed operator has
- been working more than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during periods of extended shutdown (e.g., at duties away from the control board),
such individuals shall not be assigned shift duty in the control room without at least a 12-hour' break preceding such an assignment. ,
4.1.4 If a reactor operator is required to work in excess of 8 .
continuous hours, he shall be periodically relieved of primary duties at the control board, such that periods of duty at the board do not exceed about 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.at a time.
4.1.5 The cognizant supervisor shall assure that overtime
- limitations procedure.
are controlled in accordance with this 5.0 Refe rences 5.1 NUREG-0,737,Section I.A.1.3
~
6.0 Attachments None
TDf-81339 TEXAS UTILITIES GENERATING COMPANY OFFICE MEMOR ANDUM Ty Distribution Gen Itcee. Texas August 20, 1981 ;
Subject Ooerator Guidelines The attached guidelines are provided for the operator who monitors equipment outside of the Ccuerol Room. These are minimum guidelines which should be used to ensure that the equipment is checked properly and consistently.
The parameters provided are subject to change as the plant nears completion.
The guidelines will be expanded as more systems come under the control of the Operations Department.
,m If you have any comments or questions, please contacti Bob Hill.
- 4. 2. U M R.R. Wistrand RRW/ /Im
- Attachments Distribution:
Messrs. T.E. Sain L.G. Barnes R.L. Fortenberry G.D. Lytle J.W. Purdy ec: Messrs. R.B. Seidel J.J. Allen R.D. Bird N.L. Terrell ARMS
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4
. . s Operator Guidelines -
General Area Inspection Notes I. Area Glemnliness A. No excessive amounts of oil buildup.
B. No trash piled in unauthorized area.
II. Plant Tours A. look
- 1. Valve packing leaking.
- 2. Fluid on the floor or equipment.
- 3. Excessive vibration in pipes or equipment.
- 4. Smoke.
- 5. Charts running and at the proper time.
B. Listen
- 1. Abnormal noise levels.
- 2. Change in noise level could indicate a change in equipment status.
C. Small
- 1. Electrical equipment overheating.
- 2. Smoke.
D. Touch
- 1. Exces 1ve vitration.
- 2. Heat - If you can only hold your hand on 1. _
about 10 seconds, it is about 1200F.
- 3. If in doubt about an electrical component, do not touch it with the op.n side of your hand.
i
l Operator Guidelines Equipmen: Inspection Notes I. Battery Charger Rooms A. Batteries on float.
- 1. Float voltage should be between 125-135 volts.
- 2. If the chargers are supposed to be on equalize, the voltage should be between 134-145 volts.
B. Verify that the Charger AC and DC low voltage lights are on.
The lights go out if a low voltage condition exists.
C. Ensure that there are no blown fuses on chargers.
D. DC switchboards. *
- 1. Test for ground.
- 2. Check for:
- a. Ground Protection relay lights.
- b. Undervoltage relay lights.
- c. Overvoltage relay lights.
E. Verify proper room temperature and ventilation. Room temperature should be between 500F to 1200F.
II. Battery Electrolyte, check for:
- 1. Level in the individual cells.
- 2. L akage out of a cell.
- 3. Any splattering on the top of cells.
- 4. Proper room ventilation and a room temperature between 600 and 900F.
Page 2 Rev. 0
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III. Instrument Air Compressors A. Cooling Water Pressure ,
- 1. Unit trip temporarily set at 20 psig.
- 2. Max. pressure should not cr: sed 75 psig.
B. 011, check for:
- 1. Oil level.
j
' 2. Oil pressure shouic. be between IJ to 40 psig.
Unit trips below 5 psig.
- C. Inlet Air Filter D/P indicator should normally be yellev in color.
t It turns to red on high D/P.
D. Cooling Water Temp. on head discharge should be 10 to 150F above inlet air temp. (Thermometers are being installed to meet this requirement)
E. Check Aftercooler moisture trap for excessive moisture buildup.
F. Perfor glamp check on Control Panel.
G. Verify Instrument Air header press. of about 95 to 100 psig.
H. Check Instrument Air Receivers for excessive moisture buildup.
IV. Instrument Air Dryers A. Profilter and afterfilter D/P.
- 1. Profilter high D/P alarms at 7 psid. -
- 2. After ft .er high D/P alarms at 10 paid.
- 3. Check prefilter automatic moisture drain for excessive moisture.
C. Verify proper purge air flow of about 125 CFM.
D. Check for bypass air flow through the humidistat.
E. Check tower in regeneration for overheating. Heaters must be reset on control panel if heaters have tripped out on
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V. Service Air Compressor A. Check the Inlet air filter D/P.
- 1. Normal about 2 to 3 paid.
- 2. High D/P exists at 6 paid.
B. Check the cooling water discharge temperature.
C. Oil, check for:
- 1. Oil Level.
- 2. Oil Pressure.
a.
18 psig decreasing, the W41ary Lube Oil Pump starts.
- b. 15 psig decreasing, the unit trips.
- 3. D/P across the oil filter.
- a. Normal D/P about 2-3 psi.
- b. Max. D/P of 20 psi indicates filter is dirty and should be changes.
- 4. Oil Temperature, at 125*F increasing the unit is tripped.
D. Verify that the Service Air header pressure is about 100 psig.
E. Check the air cooler moisture traps for excessive moisture buildup.
F. Perform a lamp check on control panel.
G. Check the Service Air Receiver for excessive moisture buildup.
VI. TPG, check for:
A. Pump oil levels.
B. Pump bearing slinger ring. '
C. Pump gland leakoff.
D. Pump bearing and gland temperature by touch.
E. Motor oil levels.
F. Motor inlet cooling air filters.
G. IPG heat exchanger cooling water level.
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VII. Condenser Sump, check for:
A. Sump level.
B. Proper operation of sump pumps.
VIII. Fire Protection Headers, check the:
A. Isolation valves open.
B. Header pressure.
II. Normal 6.9 KV Switchgear, ensure that the:
A. Breaker position and spring charged lamps are lit on P.hz service breaker .
y .A B. Lockout relay circuit supervisory lamps are lit.
l C. Potential transformer' fuse lamps are lit.
I. Normal 480V Switchgear, check for:
l '
A. 6.9K7 to 4807 transformer control panels for temperature and alarm indications.
B Ground detection lamps.
C. Relay . flags dropped.
II. Safeguards 6.9K7 Switchgear, ensure that the:
1 .
l A. Breaker position and spring charged lamps are lit on in j service breakers.
l 1
B. Lockout ralay circuit supervisory lamps are lit.
l Page 5 Rev.0
III. Safeguards 480V Switchgear, check for:
A. 6.9KV to 480V transformer control panels for temperature and alarm indication.
B. Ground detection lamps.
C. Relay flags dropped.
XIII. 138KV Startup Transformer IST1, look for:
A. Arcing. *
- 1. Air switches.
- 2. Connectors.
- 3. Insulators.
B. Oil leaks.
C. Oil level.
D. Temperatures.
- 1. Liquid temperature alarms at 90 C.
- 2. Winding temperature alarms at 1200C.
E. Nitrogen Bottle Compartment.
- 1. Nitrogen bottle pressure. Boti::e should be changed if pressure is down to about 200 psig.
- 2. Transformer nitrogen blanket pressure should be about 2 to 4 psig' depending on ambient temperature and transformer load.
F. Transformer combustible gas compartment.
- 1. Combustible gas reading. Alarm setpoint is 1%.
- 2. Sample pump rimning.
- 3. Sample flow. Normal reading is .2 to .3 LPM.
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- . - - - - - - - - - - - - - - - - ~ ~- - - - - - - - - - -
XIV. Circulating Water Intake A. Screen wash pump, check for:
- 1. Motor oil level.
- 2. Pump gland leakoff.
- 3. Header pressure.
- a. Normal pressure about 135 to 140 psig.
- b. Mav4== pressure is 150 psig.
B. Surface water makeup pump, check for:
- 1. Motor oil level.
- 2. Pump gland leakoff.
'IV. Service Water Intake A. wrvice water puinps, check for: -
- 1. Motor oil level. .
- 2. Pump gland leakoff.
- 3. Cooling water flow.
B. SSW pump house vent exhaust fans should be on.
IVI. Switchyard, look for:
A. Arcing.
- 1. Air switches.
- 2. Connectors.
- 3. Insulators. -
B. Relay house batteries for clenn14 ness and electrolyte leakage.
. C. Battery on float.
- 1. Float voltage should be between 125 to 135 volts.
- 2. If the chargets are rapposed to be on equalize, the voltage should be between 134 to 145 volts.
D. Battery Chargers, check for:
- 1. B?own fuse indi ators.
- 2. AC & DC low voltage lamps lit.
- 3. Annuniciator switch on for the in service chargers.
Pass 7 Wbvn @)
\. ., . - . _ . _ ..
t
- j. E. DC switchboard panels for ground lamp indication.
! i 7. Emergency shower and eye wash station to see if l
if is pressurized.
XVII. Demerator A.
Demerator transfer pumps, check for:
- 1. 011 level.
- 2. Pump gland leakoff.
- 3. Motor and pump bearing temperature by touch.
! 3. Verify seal water flow for the Desarator vacuum pumps.
i C. Demerator tank Icvel the setpoint on the meter face.
XVIII. Domineralized Water Transfer Pumps, check for:
A. Oil level.
B. Pump gland leakoff.
C. Motor and pump bearing temperature by touch.
1 i
(
l~
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