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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
P TEXAS UTILITIES GENERATING COMPAhT NKYWAY TOWER
- 400 NORTH OLIVE NTREET L.B. Mi
- DALLAM,TEXAM 75201 June 8, 1984
- m. .B.IL.L.Y
. R. CLE.M.EN.T..s t mu . .
TNRC-84016 Mr. Darrell G. Eisenhut Dire'ctor, Division of Licensing U.-S. Nuclear Regulatory Commission Washington, D.C. 20555
SUBJECT:
Comanche Peak S.E.S. Shift Staffing
Dear Mr. Eisenhut:
.The information provided in this transmittal is in response to your May 25, 1984 letter to Mr. M. D. Spence.
The summary of operating shif t experience for the Comanche Peak S.E.S.
transmitted to Mr. Denton on March 8, 1984 is still correct. The subject.
personnel have acquired additional preoperational testing experience at Comanche Peak during the last three months.
Texas Utilities Generating Company (TUGCO) committed to the use of experienced shift advisors at Comanche Peak in November, 1981. This commitment is detailed in the USNRC Safety Evaluation Report (SER),
Supplement No. 1, Section 13.1.2.1 and License Condition No. 6.
Five of the six shift advisors have been on site working with operating personnel both on and off shift since late 1982. A sixth shift advisor was recently added to the group to provide additional manpower in order to satisfy training requirements. Although the sixth individual has not had the same experience at Comanche Peak as have the other shift advisors, the process of integration into the operating staff has already begun and will
. proceed on an accelerated basis. He will not assume on-shift duties and responsibilities until the plant familiarization, shift integration and shift advisor training processes are adequately completed.
8406150159 840608
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{DRADOCK 05000445 PDR I
A DIVINRON OF TEXAN UTILITIEN ELECTRhr CO31PANY I(
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-TNRC-84016 l June 8, 1984' Page 2
~ Attachment 1 is information regarding Shift Advisors in response to the
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e p request included in Enclosure 2 of your May 25, 1984 letter.
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lPlease contact R. B. Seidel, Comanche Peak Operations Superintendent, at
[
(817) 897-4856 for additional information or clarification.
Sincerely, d'
l-- -BRC:kh_
, Attachments l~
c: R. Cooley U. S. Nuclear Regulatory Commission 611 Ryan Plaza Da*ve r Suite '000 F Arlington, TX 76011
.L. P. Crocker Division of Human Factors Safety
' U. S. Nuclear R gulatory Commission Washington, D.C. 20555
' T. A. Ippolito Project Director, Comanche Peak Project
- b. Division of. Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555 e
J. S. Marshall, ' Dallas (w/o attach. )
' ARMS I
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gg' TNRC-84016 .
June 8,-1984
> Attachment 1 Pagei1~
s The following. is. in response to the May 25, 1984 information request. For clarity, each request is repeated, followed by the TUGC0 response.
1.iA resume of each shift advisor which highlights his previous experience.
Response : Resumes are forwarded in ' Attachment 2.
- 2. A copy of J the procedure which describet the, duties and authority of the- shif t" advisors. and the working relationships between the' advisors and the operating shift personnel.
Response : Attachment 3 is a copy. of Procedure ODA-102, "Shif t Complement Responsibilities and Authorities". Section 4.2.6 delineates the responsi-bilities.and authorities of the shift advisors.
- 3. - A copy of the training program presented to the shif t advisors to assure they-have adequate knowledge of plant specific matters to properly perform their duties.
Re sponse : Attachment 4 is a copy of Procedure TRA-299, " Shift Advisor
-Training and Qualifications". In addition to the training program, described in this procedure, five of the six Comanche Peak shift advisors have been onsite' working with the operating personnel for approximately eighteen months. They were integrated into the operating staff in late 1982 in order to allow time for plant. familiarization,
. input into _ operational philosophies and review of procedures and programs. These shift advisors have experienced preoperational and
- hot ' functional testing as members of the shif t operating crews and have become knowledgeable of plant specific design, layout, procedures and administration and are well prepared to perform their. duties.
- 4. A copy of the written examination administered to the'shif t advisers and the -results of the examination, if available.
~ Response: Attachr.ent 5 includes copies of the three written examinations administered to the shift advisors and the results of the examinations.
5 A description of and copies of notes regarding the oral examination administered to the shift advisors. ,
Response: No oral examinations have been administered to the shift
' advisors. Plant specific technical knowledge is determined by written examinations as described in the response to request number 4. An p' oral review will be conducted as described in Procedure TRA-299, " Shift Advisor Training and Qualifications", Section 4.3.2 (see response to request number 3).
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~TNRC-84016 June 8, 1984 Attachment 1 Page 2
- 6. A description of the training ptogram presented to the operating shift crews to assure that they understand the role of the shif t advisors.
Response: Shift advisors at Comanche Peak have been integrated into operating shift crews over the past eighteen months. The position and role of shif t advisor was in place on shif t during hot functional testing and during much of the preoperational tes*ing. The operating shif t crews, therefore, have an excellent understanding of the role of the shift advisor. In order to further enhance this understanding, the role of the shift advisors will be included as a topic in the Comanche Peak Licensed Operator Requalification Training Program.
This training will include the responsibilities and duties of the shift advisors, their qualification requirements and the shift advisor training program. Trainees are subjec't to examination on these topics. This training will be conducted during requalification cycle 84-5, beginning on June 18, 1984 and concluding on July 27, 1984.
- 7. A statement regarding the medical qualification requirements for the shift advisors.
Response: TUGC0 has no specific medical qualification requirements for shift advisors. By observation of them performing their duties, we have concluded that they have no medical problems impeding that performance. The shift advisors are not licensed on the Comanche Peak plant and, therefore, can perform no licensed duties. In the event that a shift advisor becomes incapacitated while on shift, a qualified replacement will be called in. The same procedure applies to al.1 required shift crew members.
- 8. A description of the procedures that will be used to evaluate the performance of the shif t advisors during plant start up.
Response: The Operations Supervisor is responsible for evaluating the shift advisors. This evaluation is based on performance and is described in Procedure TRA-299, " Shift Advisor Traiing and Qualifications" (Attachment 4).
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-Attachment'2 Shift Advisor Resume's P' Douglas E. Burton i David R. Campbell Hubert C. Cruneney 4 Frank D. Pauli Lawrence J. Ryan
- Steve Stevens J
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_ ~ _ _
4 '-v POSITION:' Operations Shift Consultant NAME: Douglas E. Burton EDUCATION: High School Graduate EXPERIENCE: ~ Seventeen years experience in fossil and nuclear power plant startup and operation.
November 1982 to Present Senior Startup Consultant, Nuclear Startup Services, Inc.
Assigned to Comanche Peak Steam Electric Station as an Operations Shift Consultant responsibic for providing technical
, support-and advice to the Shift Supervisor and Control Room Staff on startup and operational activities of the plant.
Additional responsibilities include the preparation, review and
, revision of department administrative and operation procedures.
May 1981 - August 1982 Callaway Nuclear Plant - Jebcon, Inc.
Operations Consultant - Assigned to the Nuclear Operations Dept. with responsibilities of 1rreparation of the Normal, and Off-Normal operating procedures. Also included in the procedural task was preparation of all the local and control room alarm responses associated with the system procedure.
Further responsibilities included advising the Superintendent '
of Operations and his assistants, when' required.
May 1980 - May 1981 Traveled in North and South America.
July 1979 - May 1980 l Mechanical Startup Engineer - Volt Tech. Service At Angra I, Angra dos Ries, R.J., Brazil, assisted in writing hot functional procedures and pre-operational test procedures.
Worked with nuclear and secondary systems.
L October 1974 - July 1979 Operating Engineer at the Donald C. Cook Nuclear Plant, ;
[ Bridgman, Michigan i
' Supervised operating shif t during initial fuel loadings, refuelings, start-ups, low power physics testing, and power i operations to 100% power on both units. Supervised and trained licensed and non-licensed on-shift personnel in plant
, components and operation. Senior Reactor Operator in charge of l core alterations for initial refueling of unit. Attended i
simulator training one week each with Westinghouse, Zion, Illinois, and Combustion Engineering, Windsor Lock, Connecticut.
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July 1970 - September 1974 Unit Supervisor at Donald C. Cook Nuclear Plant In charge of unit one control room. Assisted in the
. preparation of preoperational test, normal operating, abnormal operating, emergency, and surveillance procedures. Manipulated controls during hot functional testing. Instructed license replacement candidates in mathematics and physics. Original nuclear training with Westinghouse at Waltz Mill and Saxton, Pennsylvania.
February 1967 - July 1970 Auxiliary Equipment Operator at Central Operating Company, Phillip Sporn Plant Maintained equipment outside the control room in a coal fired
-electric plant.
April 1965 - January 1967 -
U.S. Army Basic Training at Fort Knox, Kentucky and advanced training at Fort Sam Houston, Texas. Medical corpsman in the 44th Surgical Hospital Mobile Army,-Korea. Duties included medical aid, night." nurse" and ward master. Obtained the rank of Specialist Five.
' TRAINING: Westinghouse Reactor Training - Waltz Mill & Saxton, Pa 1970-71 Normal Requalification Training, D.C. Cook 1974-1979 Simulator Training, Westinghouse, Zion Ill., 1975 Simulator Training, Combustion Eng., Windsor Lock, Conn., 1977 Annual Fire Training, D.C. Cook ,
On site training at D.C.Dook by Westinghouse 1971-73 LICENSE'AND CERTIFICATION:
Westinghouse Certification 1970 Senior RO License - SOP-2236 1974 b
w t. -w POSITION: Oparati:n3 Shift Ccncultant NAME: David R. Campbell EDUCATION: High School Graduate EXPERIENCE:
Thirty Two years experience in fossil and nuclear-plant startup and operation.
November 1982 to Present Chief Startup Consultant, Nuclear Startup Services, Inc.
Assigned to Comanche Peak Steam Electric Station as an
' Operations Shift Consultant responsible for providing technical support and advice to.the Shift Supervisor and Control Room Staff on startup and operational activities of the pisnt.
Additional responsibilities include the preparation, review and revision of department administrative and operating procedures.
October 1980 to November 1982 Operations Supervisor - Indiana and Michigan Electric Co.
Responsible to the Operations Superintendent and assisted in supervision of all operating department personnel at D.C. Cook Nuclear Plant, coordinating the operation of all nuclear plant equipment in the Operations department, assisting in the formulation of policies and procedures related thereto, and coordinating the work of the Operations Department with other plant departments, Indiana and Michigan-Electric, and American Electric Power Service Co_rporation's System Operations
, Department.
1972 to 1980 Operation-Shift Supervisor, Indiana and Michigan Electric Co.
Responsible for the supervision of all operating shift i'
personnel and activities at D.C. Cook Nuclear Plant, a twin unit Westinghouse PWR including:
e Initial flushing following construction e Hot Functional Testing
, e Initial Criticality.
e Nine Core burnups and subsequent refuelings.
1970 to 1972 Reactor Operating Engineer, Indiana and Michigan Electric Co.
Responsible for providing technical support during the construction place of D.C. Cook Nuclear Plant, Unit 1, a 1050 MW Westinghouse PWR.
1952 to 1972 Unit Foreman, American Electric Power Co.
Responsible for the startup and operation of six fossil fueled units at the Clifty Creek Power Plant.
i I.
ee . o; TRAINING: 1970-71 Nuclear Training at Westinghouse Waltz Mill Site.
Pa., Certified Saxton Nuclear Plant, Saxton, Pa.
1971 On-site training at D.C. Cook Plant by Westinghouse 1974 Claulator training Zion, Ill.
1976 Simulator training with C.E. at Conn.
1977 Simulater training with C.E. at Conn.
1978 Sinulator training with Zion, Ill.
Lesson learned training (TMI), Core mitigation, various other training sessions resulting from TMI 1981 TMI training on simulator at Zion, Ill.
1982 Continuous training and exams in Requalification Training Program LICENSES AND CERTIFICATION:
Certified Saxton Nuclear Plant - 1970
' Senior Reactor Operators License No. SOP-2253, 1974 6
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]: ,,g POSITION: Operations Shift Consultant NAME: Hubert C. Crummey EDUCATION: LHigh School Graduate EXPERIENCE: Eighteen years experience in nuclear power plant startup and operation.
November 1982 to Present Senior Engineer, Interfacts Inc.
.Assignad to Comanche Peak Steam Electric Station as an Operations Shift Censultant responsible for providing technical '
support and advice to the Shift Supervisor and Control Room Staff on startup and operational activities of the-plant.
Additional responsibilities include the preparation, review and revision of department administrative and operating procedures.
1980 to 1982 -
Field Supervisory Engineer, Quadrex Corporation Assigned to. rewrite and update emergency operating procedures for Prairie Island Nuclear Generating Station. Rewrote and updated control room annunciator response procedures for Prairie Island. While assigned to Grand Gulf Nuclear Station, wrote instrument calibration procedures for environmental monitoring equipment in accordance with technical specifications. Previously involved with development of an extended life plant refurbishment program for overseas utility.
1973 to 1980 Reactor Shif t Supervisor, Virginia Electric & Power Co.
Supervised operation and maintenance of S trry Units 1 and 2.
Developed the start-up matrix for Surry Unit I after an extended outage for piping support modifications. Rewrote and updated procedures reflecting post-TMI changes. Supervised preoperational and operational testing of Surry Unit 2 after steam generator replacement and major systems modifications, including addition of in-line condensate polishing system and changeout'of condenser tubing. As Assistant Control Room Operator for Surry Units 1 and 2, conducted refuelings, performed reactor start-ups, developed and reviewed containment leak rate test procedures, and provided operational interface during acceptance of the Surry nuclear simulator.
Technician, Georgia Power Co.
Conducted preoperational testing and acceptance of electrical and mechanical systems for Hatch Nuclear Power Station.
1965 to 1973 Electronics Technician, U.S. Navy Qualified on all engineering stations for Polaris submarines.
Performed as instructor for SIW prototype, Idaho Falls, Idaho.
Operated and maintained electronic systems at Puget Sound Naval Communications Station. Supervised the reactor controls division and maintained and operated the reactor plant systems for SIW prototype and U.S.S. Nathan Hale.
c
'4 -q TRAINING: State of Virginia Fire Fighting School, Ashland, Virginia Westinghouse Nuclear Training, Zion, Illinois
' Reactor Operator School and Senior Reactor Training, Surry Power Station, Surry, Virginia U.S. Navy:
e Nuclear Prototype, Idaho Falls, Idaho e Nuclear Power School, Mare Island, California e Electronics Technician School, Great Lakes, Illinois Transistor Theory School, Pearl Harbor, Hawaii
-LICENSE AND CERTIFICATION:
Reactor Operators License 1975 Senior Reactor Operators License No. SOP-3544 O
e e
e ..w POSITION: Operations Shift Consultant NAME: Frank D. Pauli EDUCATION: High School Graduate Plus One Year Junior College EXPERIENCE: Fourteen years Commercial Nuclear Experience.
May 1984 to Present Senior Engineer, Interfacts, Inc.
Assigned to Comanche Peak Steam Electric Station as an Operations Shift Consultant responsible for providing technical support and advice to the Shift Supervisor and Control Room Staff on startup and operational activities of the plant. Additional responsibilities include the preparation, review and revision of department administrative and operating procedures.
August 1983 - May 1984 Shift Supervisor, Waterford III '
Supervised Plant Operations including the-Cold Hydro, Hot Functional and Pre-Operational Testing in preparation for initial fuel load.
Received Cold License Training in preparation for NRC examination.
In addition, was responsible for redesign and implementation of a Control Modification that included new operators consoles
, (3), a totally new Shift Supervisor's office and administrative area, new computer terminals at all new communications facilities.
May 1982 - August 1983 Senior Supervisory Engineer, Quaderex Corporation Consultant Shif t Supervisor responsible for Shif t Operations and testing implementation.
19.76 - May 198.!
Shift Engineer, SRO, Commonwealth Edison, Zion 1 and 2 Responsible for all plant operations, Zion 1 and 2 (3250MWt each)
Commercial Operation. In addition, functioned as Relief Operations Superintendent for Units I, II, Radwaste and Fuel Handling.
This covered a period of approximately nine (9) months.
1973 - 1976 Shift Foreman, SRO, Zion 1 and 2 Second in command for all plant operations.
1972 - 1973 R,eac$r Operator, RO, Zion 1 and 2 (Hot License Unit 1, Cold License Unit 2). Performed first cri-ticality Units 1 and 2 , first dilution to critcality Unit 2 and initial synchronization to grid for both units. In addition, performed day-to-day normal shif t functions.
1972 - 1973 Equipment Operator, Zion 1 and 2 Responsible for Turbine, Generator and Auxiliaries and all High Voltage Switching.
- 1971 - 1972
. Equipment Attendant, Zion 1 and 2 Responsible for inplant equipment in support of Shift Operations.
1970 - 1971 Equipment Attendant, Quad Cities 1 and 2 Commonwealth Edison Company Responsible for inplant equipment in support of Shift Operations.
Prior to 1970 Non-related to Commercial Nuclear Power.
TRAINING: Westinghouse Nuclear Training Center Phases I, 11 and III Reactor Operator, Zion, Unit I (Hot License), 1973 Reactor Operator, Zion, Unit II (Cold License), 1973 Senior Reactor Operators, Zion Units I and II, 1973 h
I e
m POSITION: Op;r:tions Shift Consulte:t
.NAME: Lawrence J. Ryan EDUCATION: High School Graduate EXPERIENCE: 21 years experience in Nuclear Power Plant Startup and Operation November 1982 to Present Senior Enaineer, Westinthouse NSID Assigned to Comanche Peak Steam Electric Station as an =
Operations Shift Consultant responsible for providing technical support and advice to the Shift Supervisor and Control Room Staff on startup and operational activities of the plant.
Additional responsibilities include the preparation, review and revision of department administrative and operating procedures.
a 1982 Westinsbouse Instructor Teach Reactor Theory and Nuclear Power Plant Operations at J.M.
Farley, Comanche Peak, and Millstone III sites.
1973 to 1981 Chief Nuclear Operator, Nuclear Operator Assistant Nuclear operator Operator at Cyrstal River Nuclear Plant during construction and startup to commercial ope'ations. r L
1972 to 1973 Eeuipment Attendant Operator at Zion Nuclear Plant during construction and startup to commercial operations.
1971 to 1972 Eeuipment Attendant Operator at Quad Cities Nuclear Plant During construction and initial fuel load. -
1970 Journeyman Welder All position stick and wire feed.
1962 to 1970 U.S. Navy l
NMI(SS) Qualified on submarines, qualified navy .iver, qualified nuclear welder, qualified mechanical operator on navy j nuclear power plants.
} TRAINING: Navy Machinist Mate "A" School - Study of steam plant technology, including aux equipment and main propulsion.
Navy Submarine School - Study of electrical, mechanical pneumatic and hydraulic systens on submarines.
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Navy Nuclvr Power School - Nuciccr Power Plcnt Th: cry and 4
Technology.
Navy Weltiing School - Study of metallurgy, welding techniques and Certification by x-ray for carbon steel and stainless steel pipes in all positions of welding.
4-Navy Driving School - Study of physics and diving techniques and Certification to 130 ft. in scuba 60 ft. in deip sea driving rig.
Commercial BWR Technology - Study of Systems and Theory of Operations at Quad Cities Nuclear Plant.
Commercial PWR Technology - Study of System.e. and Theory of t
Operations of a Westinghouse Plant at Zion !!uclear Plant.
Commercial PWR Technology - Study of Systens and Theory of a B&W OTSG Plant, Hot License Training, Pool Reactor Training.
1 Simulator Training and holder of a RO-4494 and SRO-3774 License at Crystal River Nuclear Plant.
Commercial PWR Technology - SRO Certific2 tion on a Westinghouse "SNUPPS" Unit and certified Step II Instructor with Westinghouse's Nuclear Training Division.
LICENSES AND CERTIFICATIONS:
Reactor Operator License No. OP-4494 Senior Reactor Operator License No. 50P-3774 Senior Reactor Operator Certification - Westinghouse 4
POSITION: . Operations Shift Consultant
.NAME: Steve Stevens EDUCATION: High School Graduate A.A. degree in Business EXPERIENCE: Eighteen years experience in Nuclear Power Plant startup and operation.
November 1982 to Present Senior Engineer, Interfacts, Inc.
Assigned to Comanche Peak Steam Electric Station as an Operations Shift Consultant responsible for providing technical support and advice to the Shift Supervisor and Control Room Staff on startup and operational activities of the plant.
Additional responsibilities include the preparation, review and revision of department administrative and operating procedures.
March 1979 to November 1982 Operations Coordinator, Virginia Electric Power Co.
Responsible to the Superintendent of Operations for the Surry Generating Station. Served as the alternate to the Operations Superintendent for all duties of that position in his absence.
Served as overall Refueling Coordinator for the last six refuelings of Units I and II. Currently licensed as a Senior Reactor Operator on both Units I and II.
January 1977 to March 1979 Shif t Supervisor, Virginia Electric Power Co.
Responsibility of directing day to day operations of operating shift. Supervised the activities of up to seven plant operators. Coordinated ~ shift activities of all plant departments.
, May 1974 to January 1977 Assistant Shift Supervisor, Virginia. Electric Power Co.
Directed the day to day activities of plant operations under the direction of the shift supervisor. While serving in the capacity of shift supervisor, was responsible for correctly identifying a steam generator tube rupture accident and bringing the plant to a safe shutdown condition. Obtained SRO License on Unit I and II in July, 1974. Participated in ten refuelings on Surry Units I aca II.
- January 1973 to May 1974 Control Room Operator, Virginia Electric Power Co.
Responsible for operation of plant equipment, performing startup and shutdown and other reactivity changes, directed the activities of auxiliary operators on shift. As a control room operator, participated in refueling operations.
.1
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Octeber 1971 to Jcnu:ry 1973 Assistant Control Room Operator, Virginia Electric Power Co.
Responsible for operation of various plant equipment.
October 1965 to October 1971 U.S. Navy - Machinist Mate Served on various nuclear powered submarines.
TRAINING: Reactor Operator and Senior Reactor Operator training, Surry Units 1 & 2 Requalification Training Navy Nuclear Power School Navy Machanist Mate School LICENSES AND CERTIFICATION:
Reactor Operator License Senior Reactor Operator License No. SOP-2216 e
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Attachment 3 ODA-102 Shift Complement Responsibilities and Authorities