Letter Sequence RAI |
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MONTHYEARML20248A1211998-05-22022 May 1998 Forwards Request for Addl Info Re 970515 Proposed License Amend to Convert Current TSs for Comanche Peak Steam Electric Station,Units 1 & 2 to Improved Standard TS Project stage: RAI ML20249B0121998-06-17017 June 1998 Forwards RAI Re Proposed Conversion to Improved Std TSs for Plant,Units 1 & 2.Response Requested within 30 Days of Receipt of Ltr Project stage: RAI ML20236K8121998-07-0707 July 1998 Requests Addl Info Based on Review of Selected Portions of Application.Addl Info Needed in Section 2.0,safety Limits & Section 3.0,limiting Condition for Operation Applicability Surveillance Requirement Applicability Project stage: Approval ML20236R3021998-07-14014 July 1998 Forwards Request for Addl Info Re Proposed Conversion to Improved Std TS for Plant,Units 1 & 2 Project stage: RAI ML20236R0431998-07-15015 July 1998 Forwards Request for Addl Info on Proposed Conversion to Improved Standard TSs for Comanche Peak Steam Electric Station,Units 1 & 2 Project stage: RAI ML20236T1311998-07-17017 July 1998 Requests Addl Info on Util Proposed License Amend to Convert Current TSs for Plant,Units 1 & 2 to Improved Std Tss.Addl Info Needed in Section 3.3, Instrumentation Project stage: Other ML20236T1871998-07-22022 July 1998 Forwards RAI on Proposed Conversion to Improved Std TSs for Plants,Units 1 & 2,per .Response Requested within 30 Days of Date of Ltr Project stage: RAI ML20237C4401998-08-14014 August 1998 Forwards RAI Re 970515 Proposed License Amend to Convert Current TSs for Plant,Units 1 & 2 to Improved Std Tss. Response to Questions Pertaining Plant,Units 1 & 2 Requested within 30 Days of Date of Ltr Project stage: RAI ML20239A2821998-09-0303 September 1998 Forwards RAI Re Proposed License Amend to Convert Current TSs for Plant,Units 1 & 2,to Improved Std Tss.Response Info Needed in Section 3.8 & Subsections 3.4 Through 3.8. Response Requested within 30 Days of Date of Ltr Project stage: RAI ML20154G3421998-10-0707 October 1998 Forwards Request for Addl Info Re Proposed Conversion to Current TS for CPSES Units 1 & 2 to Improved Ts.Response Requested within 30 Days of Ltr Date Project stage: RAI TXX-9901, Forwards Comments on Draft SE Re Proposed Conversion to ISTS1999-02-0303 February 1999 Forwards Comments on Draft SE Re Proposed Conversion to ISTS Project stage: Draft Other 1998-07-17
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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:OUTGOING CORRESPONDENCE
MONTHYEARML20217M5711999-10-20020 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 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 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 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 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 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 ML20211C4571999-08-16016 August 1999 Forwards Omitted Subj Page of Contractor TER 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 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 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 ML20210K2321999-07-29029 July 1999 Forwards Insp Repts 50-445/99-12 & 50-446/99-12 on 990530-0710.No Violations Noted 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 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 ML20209H7501999-07-15015 July 1999 Forwards Safety Evaluation on GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Comanche Peak Steam Electric Station,Units 1 & 2 ML20209G7421999-07-0808 July 1999 Forwards SER Concluding That Licensee Individual Plant Exam of External Events Process Capable of Identifying Most Likely Severe Accidents & Severe Accident Vulnerabilities & IPEEE Met Intent of Supp 4 to GL 88-20 ML20196L0121999-07-0808 July 1999 Forwards Safety Evaluation Granting First 10-Year Interval Inservice Insp Requests for Relief B-6 (Rev 2),B-7 (Rev 2), B-12,B-13,B-14 & C-9,pursuant to Tile 10CFR50.55a(g)(6)(i) ML20196K6771999-07-0202 July 1999 Ack Receipt of & Encl Scenario for Comanche Peak Steam Electric Station Emergency Plan Exercise Scheduled for 990721-22.Determined That Exercise Scenario Sufficient to Meet Emergency Plan Requirements & Exercise Objectives ML20196J4881999-06-29029 June 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1,NRC Revised Info in Rvid & Releasing Rvid as Version 2 ML20196J0401999-06-29029 June 1999 Forwards Safety Evaluation Re Plant,Units 1 & 2 Proposed Changes to Emergency Plan ML20196E6641999-06-22022 June 1999 Forwards Insp Repts 50-445/99-11 & 50-446/99-11 on 990418- 0529.No Violations Noted.Licensee Conduct of Activities Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance & Acceptable Radiological Control ML20207H3801999-06-0909 June 1999 Forwards Insp Repts 50-445/99-08 & 50-446/99-08 on 990503-11.Violations Identified & Being Treated as Noncited Violations ML20195G3771999-06-0909 June 1999 Ack Receipt of Ltr & Encl Objectives for Comanche Peak Steam Electric Station Emergency Plan Exercise Scheduled for 990721.Based on Review,Nrc Determined That Exercise Objectives,Appropriate to Meet Plan Requirements ML20207G3291999-06-0707 June 1999 Ack Receipt of Which Transmitted Rev 27 to Comanche Peak Steam Electric Station EP Under Provisions of 10CFR50.54(q).Based on Determination That Changes Do Not Decrease Effectiveness of EP No NRC Approval Required ML20207E9291999-06-0202 June 1999 Discusses 990526 Request That USNRC Exercise Discretion Not to Enforce Compliance with TS 4.8.2.1e Re Performance of Battery Performance Discharge Test,In Lieu of Battery Svc Test.Concludes Action Satisfactory & Discretion Exercised ML20207D7111999-05-28028 May 1999 Advises That Info Contained in Licensee 990514 Submittal Re License Amend Request 98-01-0 Will Be Withheld from Public Disclosure,Per 10CFR2.790. 10CFR2.790 ML20207D7011999-05-27027 May 1999 Advises That Info Contained in TU Electric 990514 Submittal (TXX-99115) Re License Amend Request 98-010 Will Be Withheld from Public Disclosure (Ref 10CFR2.790),per 990511 Application & Affidavit ML20207B7241999-05-25025 May 1999 Advises That Info Contained in Application & Affidavit 990507 (CAW-99-1333),submitting WCAP-15004,dtd Dec 1997,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20206Q0031999-05-14014 May 1999 Forwards Safety Evaluation Accepting Licensee Response to GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Comanche Peak Steam Electric Station,Unit 1 ML20206P5961999-05-12012 May 1999 Forwards Insp Repts 50-445/99-09 & 50-446/99-09 on 990419- 23.No Violations Noted.Nrc Determined That Releases of Radioactive Waste Effluents Controlled,Monitored & Quantified Well ML20206N7061999-05-12012 May 1999 Informs That NRC Ofc of NRR Reorganized,Effective 990328. Reorganization Chart Encl ML20206S5841999-05-11011 May 1999 Forwards Insp Repts 50-445/99-07 & 50-446/99-07 on 990307-0417.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint & Acceptable Radiological Controls ML20206K0311999-05-0707 May 1999 Informs That on 990407,NRC Administered Gfes of Written Operator Licensing Exam.Licensee Facility Did Not Participate in Exam,However,Copy of Master Exam with Answer Key Encl for Info,Without Encl ML20206H1701999-05-0606 May 1999 Forwards Copy of Exemption & Safety Evaluation Supporting Requirement in App K to 10CFR50.Proposal Will Use New Feedwater Flow Measurement Sys to Allow More Accurate Measurement to Thermal Power ML20206K3931999-05-0505 May 1999 Ltr Contract,Task Order 41, Comanche Peak Safety System Engineering Insp, Under Contract NRC-03-98-021 ML20206G1221999-05-0303 May 1999 Discusses 981215 Request That Document, Responses & Further Clarifications to NRC Questions from 980929 Meeting, Be Withheld from Public Disclosure.Determined Information to Be Proprietary & Will Be Withheld from Public Disclosure ML20206F5711999-04-30030 April 1999 Forwards Insp Repts 50-445/99-06 & 50-446/99-06 on 990329-0402.No Violations Noted.Insp Re Focus on Radiation Protection Program Activities During Unit 2 Refueling Outage ML20206E5211999-04-27027 April 1999 Discusses GL 96-01 Issued on 960110 & TU Responses, ,970102 & 980502 for Cpses,Units 1 & 2.Determined That Submittals Provided Both Info Requested & Responses Required by GL 96-01 ML20206B3831999-04-23023 April 1999 Forwards FEMA Final Rept for 990311,Comanche Peak Steam Electric Station Medical Drill.No Deficiencies or Areas Requiring Corrective Actions Identified ML20206B5321999-04-22022 April 1999 Ack Receipt of Ltrs Dtd 970407,09 & 0204,which Transmitted Revs 6 & 7 to Safeguards Continency Plan,Rev 10 to Security Training & Qualification Plan & Rev 29 to Physical Security Plan Submitted Under Provisions of 10CFR50.54(p) ML20206A2301999-04-14014 April 1999 Refers to Public Meeting Conducted on 990329 in Glen Rose, Tx Re Results of Plant Performance Review Completed on 990211 & Transmitted to Licensee on 990319.List of Attendees Encl ML20205L8711999-04-0707 April 1999 Forwards Insp Repts 50-445/99-03 & 50-446/99-03 on 990124-0306.No Violations Were Identified.Review of Operability Evaluation Re MOVs Disclosed That Licensee Failed to Include Info About Degraded ECCS Performance ML20205L1051999-04-0606 April 1999 Informs of Completion of Review of Tuec 980312 Submittal Re GL 97-05, SG Tube Insp Techniques. No Concerns Identified with SG Insp Techniques Employed at Cpses,Units 1 & 2,that Would Indicate Noncompliance with Current Licensing Basis ML20205F9141999-04-0101 April 1999 Informs That as of 990329 Dh Jaffe Has Been Assigned as Senior Project Manager for Plant IR 05000446/19920491999-03-24024 March 1999 Discusses Concern That Postulated Fire in CR Could Create Single Hot Short in Control Circuitry of MOVs Resulting in Spurious Operation.Required Hardware Mods Implemented to Control Circuits of Affected Mov,Per Insp Rept 50-446/92-49 ML20204F3311999-03-23023 March 1999 Forwards Discussion Items for 990323 Telcon 1999-09-07
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l T'
l Mr. C. Lcnce Terry July 15,1998
.C.- TU Electric
. Senior Vice President & Principal Nuclear Officer
! ATTN: Regulatory Affairs Department P.O. Box 1002 Glen Rose, Texas 76043
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON THE PROPOSED CONVERSION TO THE IMPROVED STANDARD TECHNICAL SPECIFICATIONS FOR COMANCHE PEAK STEAM ELECTRIC STATION, l (CPSES), UNITS 1 AND 2 (TAC NOS. M98778 AND M98779)
Dear Mr. Terry:
The Nuclear Regulatory Commission staff is reviewing TU Electric's proposed license amendment to convert the current technical specifications for the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2, to the improved Standard Technical Specifications.
TU Electric provided their proposed license amendment request by letter dated May 15,1997.
The staff has reviewed selected portions of the application. Based on its review, the staff has detem1ined that additionalinformation is needed in Section 5.0, Administrative Controls as discussed in the enclosure. S!nce you worked with three other utilities in preparing your submittal, the enclosure contains the request for additional information (RAl) questions for all four utilities. However, you need only reply to the RAI questions associated with Callaway Plant, Unit 1 as identified in the table within the enclosure.
To assist the staff in maintaining its review schedule, please respond to the questions pertaining to CPSES Units 1 and 2 within 30 days of the date of this letter. If you have any questions regarding the RAI, please contact me at (301) 415-1038. If all four utilities would like to have a common discussion, a single meeting, or phone call can be coordinated.
Sincerely, ORIGINAL SIGNED BY:
/
Timothy J. Polich, Project Manager ,
Project Directorate IV-1 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation Docket Nos. 50-445 , DISTRIBUTION: /
and 50-446 . .> ,Dochsta OGC PUBLIC ACRS
Enclosure:
Request for Additional PDIV-1 Reading PGwynn, RIV information EAdensam (EGA1) CHawes JHari on - WBeckner cc w/ encl: See next page TPolicii JLuehman
' Document Name: CPITS.RAI i
OFC PD4-1 PD4-2 TSB /, /b /2, NAME TPolich e::u EPeyto, WBeckner-DATE 7 /jf/ 98 7 /19 / 98 7 / I/98 OFFICIAL RECORD COPY
([ ([c' a' L]' a
((
u%]?
m "{a "u' {1w] 3 9807210211 980715 PDR ADOCK 05000445 P PDR
, pm aseuq p % UNITE 3 STATES g } NUCLEAR RE2ULATORY COMMISSION t WASHINGTON, D.C. 30ess 4001 i
- \*****/ July 15,1998 Mr. C. Lance Terry TU Electric Senior Vice President & Principal Nuclear Officer ATTN: Regulatoiy Affairs Department P.O. Box 1002 Glen Rose, Texas 76043
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON THE PROPOSED CONVERSION TO THE IMPROVED STANDARD TECHNICAL SPECIFICATIONS FOR COMANCHE PEAK STEAM ELECTRIC STATION, (CPSES), UNITS 1 AND 2 (TAC NOS. M98778 AND M98779)
Dear Mr. Terry:
The Nuclear Regulatory Commission staff is reviewing TU Electric's proposed license amendment to convert the current technical specifications for the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2, to the improved Standard Technical Specifications.
TU Electric provided their proposed license amendment request by letter dated May 15,1997.
The staff has reviewe:1 selected portions of the application. Based on its review, the staff has determined that additional information is needed in Section 5.0, Administrative Controls, as discussed in the enclosure. Since you worked with three other utilities in preparing your submittal, the enclosure contains the request for additional information (RAI) questions for all four utilities. However, you need only reply to the RAI questions associated with CPSES Units 1 and 2, as identified in the t'ble within the enclosure.
To assist the staff in maintaining its review schedule, please respond to the questions pertaining to CPSES Units 1 and 2 within 30 days of the date of this letter. If you have any questions regarding the RAI, please contact me at (301) 415-1038. If all four utilities would like to have a common discuss!on, a single meeting, or phone call can be coordinated.
Sincerely,
~d)fh Timothy J.Idich, Project Manager Project Directorate IV-1 Division of Reactor Projects lil/lV Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446
Enclosure:
Request for Additional Information cc w/ encl: See next page l
Mr. C. Lance Terry TU Electric Company Comanche Peak, Units 1 and 2 cc:
Senior Resident inspector Honorable Dale McPherson U.S. Nuclear Regulatory Commission County Judge P. O. Box 2159 P. O. Box 851 Glen Rose, TX 76403-2159 Glen Rose, TX 76043 Regional Administrator, Region IV Office of the Govemor U.S. Nuclear Regulatory Commission ANN: John Howard, Director 611 Ryan Plaza Drive, Suite 400 Environmental and Natural Arlington,TX 76011 Resources Policy P. O. Box 12428 Mrs. Juanita Ellis, President Austin,TX 78711 Citizens Association for Sound Energy 1426 South Polk Arthur C. Tate, Director ,
Dallas, TX 75224 Division of Compliance & Inspection Bureau of Radiation Control Mr. Roger D. Walker Texas Department of Health TU Electric 1100 West 49th Street Regulatory Affairs Manager Austin, TX 78756-3189 i P. O. Box 1002 Glen Rose, TX 76043 Jim Calloway Public Utility Commission of Texas George L. Edgar, Esq. Electric Industry Analysis Morgan, Lewis & Bocklus P. O. Box 13326 1800 M Street, N.W. Austin, TX 78711-3326 Wr hington, DC 20036-5869 i
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, FOUR LOOP GROUP (FLOG) IMPROVED TS REVIEW COMMENTS !
! , SECTION 5.0 - ADMINISTRATIVE CONTROLS
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5.1-1 CTS 6.1.1, ITS 5.1.1, Change 0101 A and Difference 5.1-2 (Callaway) )
. Comment: Difference 5.1-2 states that the STS is revised to " maintain CTS." However, given
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that Change 01-01-A Insert 1 includes new language into the CTS it is unclear how the CTS is being maintained. This addition of new language into the CTS and deviation from the STS is notjustified. ProvideJustification.
FLOG Response: .
' 5.2-1 STS 5.2.2 b and Difference 5.2-2
, Comment: TSTF-121 has been withdrawn for modification, combination and resubmission. j i- Use current ITS.
FLOG Response: j 5.3-1 ITS 5.3.1 (Wolf Creek, Callaway and Diablo Canyon)
Comment: Part 55 of Title 10 of the Code of Federal Regulations was revised in March 1987 to establish upgraded requirements for licensed reactor operators. NRC Regulatory Guide (RG) 1.8, Revision 2, April 1987, describes methods acceptable to the staff for complying with the
. revised rule. The Statements of Consideration for the Part 55 rule change state that, "Those facility licensees that have made a commitment that is less than that required by the new rules must conform to the new rules automatically." The staff is concemed some facilities continue to have technical specifications that reference older industry standards that may not fully meet the revised requirements of 10 CFR Part 55.
The staff previously considered that the standards applied through the industry's accreditation process were equivalent to the guidance contained in RG 1.8, Revision 2. However, the staff has recently found that current ENPO guidance in this area is very general; only advising licensees to follow regulatory requirements. In RG 1.8, Revision 2, the NRC staff endorses, with conditions, certain parts of industry standard ANSI /ANS-3.1-1981 as an acceptable approach for complying with the qualification and training requirements of 10 CFR Parts 50 and
- 55. This endorsement applies to the positions identified as shift supervisor, senior operator, licensed operator, shift technical advisor, and radiation protection manager. For positions other than those identified, the RG finds acceptable the approach provided in ANSI N18.1-1971.
- For Callaway, the ITS proposes to adopt the CTS which adopts ANSI /ANS 3.1-1978 for the unit staff (besides SROs, Ros and STAS) and RG 1.8, September 1975 for the radiation protection manager. For Wolf Creek, the ITS proposes to adopt the CTS which adopts ANSI /ANS 3.1-1978 for the unit staff (besides SROs and ROs) and RG 1.8, September 1975 for the radiation L
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. l l protection manager. For Diablo Canyon, the ITS proposes to adopt the CTS which adopts l
ANSl/ANS 3.1-1978 for the unit staff (besides the radiation protection manager) though it does makes a reference to Ros and SROs having to meet the minimum qualifications of Part 55.
Please describe how your commitment to an ANSI standard other than that endorsed by NRC RG 1.8, Revision 2 currently meets the requirements of 10 CFR Part 55, as discussed in the Statements of Consideration for the rule change and would meet those requirements with the j ITS as proposed.
FLOG Response:
1' 5.5-1 Change 217 LS1 (Callaway, Diablo Canyon) l Comment: WOG-85 has not yet become a TSTF. Use current ITS.
j FLOG Response:
i 5.5-2 Difference 5.5-14 l Comment: WOG-85 has not yet become a TSTF. Use current ITS.
l FLOG Response:
l l 5.5-3 ITS 5.5.4 b&g and Difference 5.51 i l
L Comment: Changes are based on a y'et unnumbered traveler. Use current ITS.
L FLOG Response: ,
i 5.5-4 ITS 5.5.4 e and Difference 5.513 Comment: WOG-72 has not yet become a TSTF. Use current ITS.
l FLOG Response:
- j l 5.5-5 ITS 5.5.12 c, CTS 6.8.5 a.3 and Difference 5.5 7 (Callaway)
Comment: The CTS Just refers to 10 CFR Part 20 Appendix B. More information is needed to !
determine which table govems the current requirements.
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t 3-FLOG Response:
5.54 CTS 3.7.6 and Changes 10-15 LG and 10-17-A (Callaway)
Comment: Please provide a better explanation of the deletion of Pressurization System 2200 CFM +800, -200.
- FLOG Response: ,
5.5 7 CTS 3.7.6 and Changes 10-15-LG and 1017 A (Wolf Creek)
Comment: The CTS markup is inconsistent with the comments as nothing is lined out.
Further, the deletions (at least as they are reflected in ITS 5.5.11) need a better explanation.
Provide explanation.
FLOG Response:
5.5-8 CTS 3.7.6 (3.7.5.1 and 3.7.6.1 DCPP and 3.7.7.1 and 3.7.8 CPSES) and Change 10 08 A l
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- Comment: it should be speciCcally noted as to which CTS requirements were carried over to the VFTP and which were deleted (as well as which section of what standard justified the duplication deletions). Provide explanation and justification, i i FLOG Response:
l 5.5 9 CTS 3.9.13 (3.9.12 - DCPP) and Change 12 04 A (Wolf Creek, Callaway and Diablo Canyon) l L
Comment: it appears that some of the CTS requirements covered by this change were deleted rather than transferred to ITS 5.5.11 as stated. Justify the individual deletions.
FLOG Response:
--5.510 ITS 5.5.11.b (Callaway and Wolf Creek)
, Comment: The smooth copy of the ITS still has the [] around the plant specific bypass value
- FLOG Response:
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Y E _ _ _ _-_----------------: 1 ----- i ----_------- - - - - - - - - - - - - - - - - - - - - - - - - - - --
. -4 5.5-11 ITS 5.5.9 d, ITS 5.5.11 b, and 5.5.13 (Diablo Canyon)
Comment: The smooth copy of the ITS contains a number of administrative errors. Page 5.0 1g of the smooth copy of the ITS has two errors. First, the VFTP section title and the (continued) appear before ITS 5.5.11.b when they should appear at the top of Page 5.0-20.
Second, in 5.5.11 b it should not be "10%at". To be consistent with the rest of the section, Page 5.0-15 should have SG Tube (continued) at the top of the page. Similarly, Page 5.0-23 should have a Diesel Fuel (continued) at the top of the page. 1 FLOG Response:
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5.512 ITS 5.5.11 and CTS 4.7.6.c.2 (Wolf Creek)
Comment: The value of relative humidity is 70% in the ITS,78% in the CTS markup, and 70%
in the CTS. Is it correct to assume the CTS markup value is wrong?
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' FLOG Response: !
l 5.5-13 Difference 5.5-9 (Diablo Canyon)
Comment: Unlike Comanche Peak, the ITS/ CTS cross reference table does not include any l reference to CTS 3/4.11. Therefore, the difference as written is not detailed enough. Either !
make the tie in the difference discussion or update the cross reference.
FLOG Response: !
l 5.5-14 ITS 5.5.11.e and CTS 4.7,8.d.3 (Comanche Peak) ;
1 Comment: The value for the ESF filtration unit is 100 plus or minus 5 kW in the CTS and 100 i
plus 5 kW in the ITS. Provide correction orjustify change.
! FLOG Response; 4
l 5.5-1 ITS 5.8.5 a.7&8, Changes 0314&15 M
! Comment: it is true that the additions would make the COLR more restrictive however, the removal of the specific values from the TS is a less restrictive change that needs to be justifed.
Provide justification.
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5.6-2 Difference 5.6-2 (Diablo Canyon) I l Comment: TSTF-37 has not yet been approved by the NRC. Use current ITS.
FLOG Response:
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! 5.71 ITS 5.7.2 and Difference 5.7-2 l i l l Comment: TSTF-167 has been rejected by the NRC. Use current ITS. ;
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e FLOG RAI APPLICABILITY TABLE FOR ITS SECTION 5.0 RAI Number Callaway Comanche Peak Diablo Canyon Wolf Creek 5.1-1 X 5.2-1 X X X X 5.3-1 X X X 5.5-1 X X 5.5-2 X X X X 5.5-3 X X X X 5.5-4 X X X X l 5.5-5 X 5.5-6 X 5.5-7 X 5.5-8 X X X X 5.5-9 X X X l 5.5-10 X X 5.5-11 X 5.5-12 X 5.5-13 X 5.5-14 X 5.6-1 X X X X 5.6-2 X 5.7-1 X X X X l
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