Letter Sequence Other |
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TAC:M98803, Modify Section 3.8 Mode Restriction Notes, TSTF-36, Battery Float Current and Battery Inspection Program, TSTF-38 (Open) |
Results
Other: ML20195C513, ML20236K821, ML20236S240, ULNRC-03889, Forwards Proposed Tech Specs Sections 1.0,2.0 & 3.0, Converting to Improved Tech Specs,In Response to NRC 980707 & 09 Rais.Response to Comment Number 1.1-4 Will Be Provided Separately After 980817 NRC Ltr to NEI Has Been Evaluated, ULNRC-03937, Responds to RAIs on Proposed Conversion to Its,Section 3.8, Electrical Power Sys, ULNRC-03946, Forwards RAI Re Proposed Conversion to Improved Tech Specs Sections 1.0,3.1,3.2,3.3,3.4,3.7,3.9 & 5.0.Suppl to Ref Will Be Provided at Later Date, ULNRC-03979, Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6,3.7,3.8,3.9 & 5.0.Suppl to Ltr Dtd 970515,will Be Provided at Later Date, ULNRC-04007, Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6 & 3.7.Encl Includes mark-ups of ITS Sections 3.5,3.6 & 3.8.Suppl to Ltr Will Be Provided at Later Date, ULNRC-04018, Submits follow-up Items Re Proposed Conversion to ITS Sections 1.0,3.3,3.4,3.6,3.7 & 3.9.Suppl to Ltr Will Be Submitted at Later Date
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MONTHYEARML20248E8441998-05-22022 May 1998 Forwards RAI on Proposed Conversion to Improved Std TS for Plant,Unit 1 in Section 3.6.Response Requested within 30 Days of Date of Ltr Project stage: RAI ML20249B4571998-06-16016 June 1998 Forwards Request for Addl Info Re Licensee Amend to Convert Current TS for Callaway Plant,Unit 1 to Improved Ts,Provided by Project stage: RAI ML20249B5301998-06-17017 June 1998 Forwards Request for Addl Info on 970515 Proposed License Amend to Convert Current TSs for Callaway Plant,Unit 1 to Improved Standard TSs Project stage: RAI ULNRC-03853, Forwards Info & TS Pages Re 980522 Application for Amend to License NPF-30,converting to Improved Sts,In Response to NRC Request for Addl Info.Suppl to Util Will Be Provided at Later Date1998-06-26026 June 1998 Forwards Info & TS Pages Re 980522 Application for Amend to License NPF-30,converting to Improved Sts,In Response to NRC Request for Addl Info.Suppl to Util Will Be Provided at Later Date Project stage: Request ML20236K8211998-07-0707 July 1998 Requests Addl Info on Proposed Conversion to Improved Std Tss.Response Requested within 30 Days of Date of Ltr Project stage: Other ML20236P3091998-07-0909 July 1998 Forwards RAI Re Proposed Conversion to Improved TS for Plant,Unit 1.Addl Info Needed in Section 1.0, Use & Application. Response Requested within 30 Days of Receipt of Ltr Project stage: RAI ML20236Q6711998-07-15015 July 1998 Forwards Request for Addl Info on Proposed Conversion to Improved Standard TSs for Callaway Plant,Unit 1 Project stage: RAI ML20236S2401998-07-17017 July 1998 Requests Addl Info on Proposed License Amend to Convert Current TS to Improved Standard TS for Callaway Plant, Unit 1 Project stage: Other ML20236S2201998-07-21021 July 1998 Forwards RAI Re Util Proposed License Amend to Convert Current TSs for Plant,Unit 1 to Improved Tss.Response Requested within 30 Days of Receipt of Ltr Project stage: RAI ULNRC-03877, Submits Response to NRC RAI Re Proposed Conversion to Improved TSs Sections 3.1,3.2,3.5,3.9 & 4.0.Suppl to Will Be Provided at Later Date1998-08-0404 August 1998 Submits Response to NRC RAI Re Proposed Conversion to Improved TSs Sections 3.1,3.2,3.5,3.9 & 4.0.Suppl to Will Be Provided at Later Date Project stage: Response to RAI ML20237C4251998-08-14014 August 1998 Forwards RAI Re Proposed License Amend to Convert Current TSs for Plant,Unit 1 to Improved Std Ts,Per 970515 Request. Response Requested within 30 Days of Date of Ltr Project stage: RAI ULNRC-03889, Forwards Proposed Tech Specs Sections 1.0,2.0 & 3.0, Converting to Improved Tech Specs,In Response to NRC 980707 & 09 Rais.Response to Comment Number 1.1-4 Will Be Provided Separately After 980817 NRC Ltr to NEI Has Been Evaluated1998-08-27027 August 1998 Forwards Proposed Tech Specs Sections 1.0,2.0 & 3.0, Converting to Improved Tech Specs,In Response to NRC 980707 & 09 Rais.Response to Comment Number 1.1-4 Will Be Provided Separately After 980817 NRC Ltr to NEI Has Been Evaluated Project stage: Other ML20151U9221998-09-0303 September 1998 Forwards Request for Addl Info Re Util Proposed License Amend to Convert Current TSs for Callaway Plant,Unit 1 to Improved Standard Tss, Project stage: RAI ULNRC-03900, Forwards Response to NRC 980715 & 0721 RAIs Re Util 970515 Application for Amend to License NPF-30 to Convert to Improved TS Sections 3.4 & 5.01998-09-24024 September 1998 Forwards Response to NRC 980715 & 0721 RAIs Re Util 970515 Application for Amend to License NPF-30 to Convert to Improved TS Sections 3.4 & 5.0 Project stage: Request ML20154J0101998-10-0707 October 1998 Forwards RAI Re Licensee Proposed Amend to Convert Current TSs for Plant,Unit 1 to Improved Std Ts.Addl Info Required in Section 3.8,Subsections 3.8.1,3.8.2,3.8.3,3.8.9 & 3.8.10. Response Requested within 30 Days of Date of Ltr Project stage: RAI ULNRC-03908, Forwards Response to NRC RAI Re Proposed Amend to License NPF-30,converting to Improved Tech Specs.Proposed Sections 3.1,3.2,3.4,3.5 & 5.0 Also Encl1998-10-21021 October 1998 Forwards Response to NRC RAI Re Proposed Amend to License NPF-30,converting to Improved Tech Specs.Proposed Sections 3.1,3.2,3.4,3.5 & 5.0 Also Encl Project stage: Response to RAI ULNRC-03905, Forwards Response to RAI on Proposed Conversion to Improved TS Section 3.7, Plants Sys1998-10-21021 October 1998 Forwards Response to RAI on Proposed Conversion to Improved TS Section 3.7, Plants Sys Project stage: Response to RAI ULNRC-03927, Forwards Response to NRC RAI Re TS Section 3.3, Instrumentation, Converting to Improved Tech Specs. Requested Info Is Encl as Well as Any Addl Changes Needed for Section 3.3 as Identified by Licensee1998-11-25025 November 1998 Forwards Response to NRC RAI Re TS Section 3.3, Instrumentation, Converting to Improved Tech Specs. Requested Info Is Encl as Well as Any Addl Changes Needed for Section 3.3 as Identified by Licensee Project stage: Response to RAI ULNRC-03937, Responds to RAIs on Proposed Conversion to Its,Section 3.8, Electrical Power Sys1998-12-11011 December 1998 Responds to RAIs on Proposed Conversion to Its,Section 3.8, Electrical Power Sys Project stage: Other ULNRC-03946, Forwards RAI Re Proposed Conversion to Improved Tech Specs Sections 1.0,3.1,3.2,3.3,3.4,3.7,3.9 & 5.0.Suppl to Ref Will Be Provided at Later Date1998-12-22022 December 1998 Forwards RAI Re Proposed Conversion to Improved Tech Specs Sections 1.0,3.1,3.2,3.3,3.4,3.7,3.9 & 5.0.Suppl to Ref Will Be Provided at Later Date Project stage: Other ML20203C5271999-02-0505 February 1999 Forwards follow-up Items Re Proposed Conversion to Improved TS Sections 1.0,3.2,3.3,3.4,3.6,3.7,3.8,3.9 & 5.0.Submittal Not Supplement to 970517 Amend Request & Not Reviewed by Onsite Review Committee or Nuclear Safety Review Board Project stage: Supplement ULNRC-03979, Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6,3.7,3.8,3.9 & 5.0.Suppl to Ltr Dtd 970515,will Be Provided at Later Date1999-03-0909 March 1999 Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6,3.7,3.8,3.9 & 5.0.Suppl to Ltr Dtd 970515,will Be Provided at Later Date Project stage: Other ULNRC-04007, Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6 & 3.7.Encl Includes mark-ups of ITS Sections 3.5,3.6 & 3.8.Suppl to Ltr Will Be Provided at Later Date1999-04-0707 April 1999 Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6 & 3.7.Encl Includes mark-ups of ITS Sections 3.5,3.6 & 3.8.Suppl to Ltr Will Be Provided at Later Date Project stage: Other ULNRC-04018, Submits follow-up Items Re Proposed Conversion to ITS Sections 1.0,3.3,3.4,3.6,3.7 & 3.9.Suppl to Ltr Will Be Submitted at Later Date1999-04-21021 April 1999 Submits follow-up Items Re Proposed Conversion to ITS Sections 1.0,3.3,3.4,3.6,3.7 & 3.9.Suppl to Ltr Will Be Submitted at Later Date Project stage: Other ULNRC-04024, Suppl 1 to Application to License NPF-30,adding License Conditions to Address Surveillance Requirements as Described in Ltr1999-04-30030 April 1999 Suppl 1 to Application to License NPF-30,adding License Conditions to Address Surveillance Requirements as Described in Ltr Project stage: Request ML20195C5131999-05-28028 May 1999 Forwards Revs to Sections 3.9 & 5.6 of Its,Based on Resolution Telcons Held Between NRC Staff & Util on 990526 & 27 Project stage: Other 1998-07-07
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K1051999-10-19019 October 1999 Ack Receipt of Ltr Dtd 990707,which Transmitted Rev 29 to Callaway Plant Physical Security Plan,Under Provisions of 10CFR50.54(p).Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required ML20217G2071999-10-14014 October 1999 Forwards Insp Rept 50-483/99-10 on 990913-16.No Violations Noted.Insp Was to Review Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise ML20217B5901999-10-0505 October 1999 Informs That Staff Concludes That Licensee Responses to GL 97-06 Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Callaway Plant,Unit 1 ML20217B5711999-10-0505 October 1999 Discusses GL 98-01 Issued by NRC on 980511 & Uec Responses for Callaway NPP Unit 1 ,990224 & 990628.Informs That Staff Reviewed Responses & Concluded That All Requested Info for GL 98-01 Provided ML20212G0221999-09-22022 September 1999 Forwards Insp Rept 50-483/99-11 on 990812-20.No Violations Noted.Team Found,Weakness in flow-accelerated Corrosion Monitoring Program Resulted in No Previous Insp of Pipe Segment Which Failed ML20212D9341999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of Callaway Plant.In Area of Ep,C/As Taken in Response to Problems Identified During Previous Exercises Warrant More in-dept Review.Details of Insp Plan Through March 2000 Encl ML20217D5791999-09-15015 September 1999 Provides Formal Documentation of Reviews & Discussions Re Technical Ltr Rept for Proprietary Info.Review of Ltr Was Discussed in Telcon & Via e-mail Messages. Summary of Telcons as Documented on 990708,included ML20212A4921999-09-13013 September 1999 Forwards Insp Rept 50-483/99-08 on 990725-0904.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20212A4701999-09-10010 September 1999 Rssponds to NRC 990709 RAI Re Util Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection Iwe. Acceptance Criteria for Liner Plate Pressure Boundary Thickness Will Be Limited to 10% Nominal Thinning ML20212B1521999-09-10010 September 1999 Forwards Insp Rept 50-483/99-07 on 990809-13.No Violations Noted.Inspectors Used Annual Licensed Operator Requalification Exams to Assess Licensed Operator Performance ML20211N0321999-09-0202 September 1999 Forwards SE Concluding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20211B0241999-08-18018 August 1999 Ack Receipt of Ltr Dtd 990714,transmitting Scenario for Licensee Upcoming Biennial Exercise.Based on Review,Nrc Determined That Exercise Scenario Sufficient to Meet Emergency Plan Requirements & Exercise Objectives ML20210T9121999-08-13013 August 1999 Forwards Insp Rept 50-483/99-06 on 990613-0724.One Severity Level 4 Violation Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20210R7241999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data Rept for Callaway Nuclear Plant for 990101-990630,IAW 10CFR26.71(d) 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 ULNRC-04085, Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power1999-08-11011 August 1999 Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power ML20210P0371999-08-10010 August 1999 Forwards SE Granting Licensee 980710 Requests for Relief (ISI-13 - ISI-18) from Requirements of Section XI of 1989 Edition of ASME B&PV Code for Second 10-year Interval ISI at Plant,Unit 1 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 ULNRC-04079, Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999 Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20210H6381999-07-30030 July 1999 Forwards SE Accepting Relief Request for Approval for Use of Alternate Exam Requirement for Plant Inservice Insp Program A93443, Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves1999-07-28028 July 1999 Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves ULNRC-04075, Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves1999-07-28028 July 1999 Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves ULNRC-04076, Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs1999-07-28028 July 1999 Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs ULNRC-04070, Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power1999-07-27027 July 1999 Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power 05000483/LER-1998-008, Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved1999-07-27027 July 1999 Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved ULNRC-04071, Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-021999-07-27027 July 1999 Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-02 ML20210B5611999-07-20020 July 1999 Forwards Review of Ltr & Encl Objectives for Plant,Unit 1,1999 Emergency Plan Exercise Scheduled for 990914 ML20210B4021999-07-19019 July 1999 Ack Receipt of Facility Emergency Plan Implementing Procedure EIP-ZZ-00101, Classification of Emergencies, Rev 23,issued on 990513,under Provisions of 10CFR50,App E, Section V ML20210B4401999-07-19019 July 1999 Ack Receipt of Revs to Facility Radiological Emergency Response Plan,Chapters 8.0 & 4.0,issued Respectively on 990512-14,under Provisions of 10CFR50,App E,Section V ML20212A3291999-07-15015 July 1999 Forwards Scenario Manual Containing Description of Callaway Plant 1999 Biennial Emergency Response Plan Exercise to Be Conducted 990914.Correspondence to Satisfy 60-day Submittal Requirement ML20209F3471999-07-0909 July 1999 Forwards Response to NRC 990624 RAI to Complete NRC Review of Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection IWE ML20209E5591999-07-0808 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.TAC MA0531 Closed ML20209H2471999-07-0707 July 1999 Forwards Rev 29 to Physical Security Plan,Per 10CFR50.54(p). Rev Withheld,Per 10CFR73.21 ML20196J9501999-07-0202 July 1999 Ack Receipt of Plant Ep,Rev 22,received on 981207 & Submitted Under Provision of 10CFR50,App E,Section V.Changes Does Not Decrease Effectiveness of EP & Continues to Meet Stds of 10CFR50.47(b).NRC Approval Not Required ML20209B6851999-06-28028 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Nuclear Power Plants. Disclosure Rept Encl ML20209C0171999-06-28028 June 1999 Forwards Special Rept 99-01 Re Fifteenth Year Inservice Containment Bldg Tendon Surveillance Failure.Observed Voids in Sheathing Filler Grease Do Not Indicate Degradation of post-tensioning Sys,Based on Encl Evaluation ML20196F8101999-06-25025 June 1999 Informs That J Donohew Will Assume Project Manager Responsibilities,Effective 990621 ML20196H2521999-06-25025 June 1999 Forwards Insp Rept 50-483/99-05 on 990502-0612.Two Violations Occurred & Being Treated as Noncited Violations, Consistent with App C of Enforcement Policy ML20196F8181999-06-24024 June 1999 Forwards RAI Re 990111 Request for Relief from Certain ASME Code ISI Requirements for Containment Liners.Response Requested within 30 Days from Date of Agreement ML20196G5621999-06-21021 June 1999 Informs NRC of Implementation of Amend 132 to Callaway License NPF-30 to Allows Installation of Electrosleeves for Steam Generator Tube Repair for Two Cycles Following Installation of First Electrosleeve IR 05000483/19990041999-06-18018 June 1999 Refers to GL 96-05 Issued by NRC on 960918,UE Responses & 970313 & NRC Insp Rept 50-483/99-04,dtd 990427. Forwards Request for Addl Info Re GL 96-05 Program at Callaway Plant,Unit 1 ML20212J2441999-06-18018 June 1999 Submits Request for Alternate Exam Requirements for Plant Re ISI Program Plan.Plant Does Not Torque Bolted Connections to Stress Values Greater than 100 Ksi ML20195H0971999-06-14014 June 1999 Discusses Une 990407 Request That Proprietary Document Entitled, Thermal Stability Assessment - Electrosleeved Tubes, Be Withheld from Public Disclosure.Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20207H3751999-06-14014 June 1999 Discusses 990407 Une Request That Proprietary Version of Document Entitled, Evaluation of Severe Accident Simulation, Dtd April 1999,be Withheld from Public Disclosure.Determined Info Proprietary & Will Be Withheld ML20195H9731999-06-11011 June 1999 Forwards Requested Addl Info Related to Relief Request ISI-16,encountered During Refuel 9 ML20195J9301999-06-0808 June 1999 Informs That Refuel 9 OAR-1 Owners Data Rept for ISI & Summary Rept for Interval 2 Was Submitted with Typographical Error,In That Commercial Service Date Should Be 841219,vice 941219.Please Substitute Encl Corrected Document ML20207G3201999-06-0707 June 1999 Ack Receipt of Change Notice 98-008 Dtd 980918,which Transmitted Changes to Callaway Plant Ep,Rev 21,under Provisions of 10CFR50,App E,Section V.No NRC Approval Required.No Violations Identified ML20207G3151999-06-0707 June 1999 Ack Receipt of Callaway Plant EP Implementing Procedure EIP-ZZ-001001M,Classification of Emergencies,Rev 22,issued on 981222 Under 10CFR50,App E,Section V Provisions.No Violations Identified ML20195C5131999-05-28028 May 1999 Forwards Revs to Sections 3.9 & 5.6 of Its,Based on Resolution Telcons Held Between NRC Staff & Util on 990526 & 27 A98803, Forwards Certified ITS & ITS Bases for Callaway Plant,In Response to NRC 990402 Draft SE for License Amend to Convert TSs to Format & Expanded Bases of ITS1999-05-27027 May 1999 Forwards Certified ITS & ITS Bases for Callaway Plant,In Response to NRC 990402 Draft SE for License Amend to Convert TSs to Format & Expanded Bases of ITS 1999-09-22
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217D5791999-09-15015 September 1999 Provides Formal Documentation of Reviews & Discussions Re Technical Ltr Rept for Proprietary Info.Review of Ltr Was Discussed in Telcon & Via e-mail Messages. Summary of Telcons as Documented on 990708,included ML20212A4701999-09-10010 September 1999 Rssponds to NRC 990709 RAI Re Util Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection Iwe. Acceptance Criteria for Liner Plate Pressure Boundary Thickness Will Be Limited to 10% Nominal Thinning ML20210R7241999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data Rept for Callaway Nuclear Plant for 990101-990630,IAW 10CFR26.71(d) ULNRC-04085, Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power1999-08-11011 August 1999 Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power ULNRC-04079, Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999 Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ULNRC-04075, Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves1999-07-28028 July 1999 Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves A93443, Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves1999-07-28028 July 1999 Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves ULNRC-04076, Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs1999-07-28028 July 1999 Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs 05000483/LER-1998-008, Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved1999-07-27027 July 1999 Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved ULNRC-04070, Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power1999-07-27027 July 1999 Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power ULNRC-04071, Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-021999-07-27027 July 1999 Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-02 ML20212A3291999-07-15015 July 1999 Forwards Scenario Manual Containing Description of Callaway Plant 1999 Biennial Emergency Response Plan Exercise to Be Conducted 990914.Correspondence to Satisfy 60-day Submittal Requirement ML20209F3471999-07-0909 July 1999 Forwards Response to NRC 990624 RAI to Complete NRC Review of Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection IWE ML20209H2471999-07-0707 July 1999 Forwards Rev 29 to Physical Security Plan,Per 10CFR50.54(p). Rev Withheld,Per 10CFR73.21 ML20209C0171999-06-28028 June 1999 Forwards Special Rept 99-01 Re Fifteenth Year Inservice Containment Bldg Tendon Surveillance Failure.Observed Voids in Sheathing Filler Grease Do Not Indicate Degradation of post-tensioning Sys,Based on Encl Evaluation ML20209B6851999-06-28028 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Nuclear Power Plants. Disclosure Rept Encl ML20196G5621999-06-21021 June 1999 Informs NRC of Implementation of Amend 132 to Callaway License NPF-30 to Allows Installation of Electrosleeves for Steam Generator Tube Repair for Two Cycles Following Installation of First Electrosleeve ML20212J2441999-06-18018 June 1999 Submits Request for Alternate Exam Requirements for Plant Re ISI Program Plan.Plant Does Not Torque Bolted Connections to Stress Values Greater than 100 Ksi ML20195H9731999-06-11011 June 1999 Forwards Requested Addl Info Related to Relief Request ISI-16,encountered During Refuel 9 ML20195J9301999-06-0808 June 1999 Informs That Refuel 9 OAR-1 Owners Data Rept for ISI & Summary Rept for Interval 2 Was Submitted with Typographical Error,In That Commercial Service Date Should Be 841219,vice 941219.Please Substitute Encl Corrected Document ML20195C5131999-05-28028 May 1999 Forwards Revs to Sections 3.9 & 5.6 of Its,Based on Resolution Telcons Held Between NRC Staff & Util on 990526 & 27 A98803, Forwards Certified ITS & ITS Bases for Callaway Plant,In Response to NRC 990402 Draft SE for License Amend to Convert TSs to Format & Expanded Bases of ITS1999-05-27027 May 1999 Forwards Certified ITS & ITS Bases for Callaway Plant,In Response to NRC 990402 Draft SE for License Amend to Convert TSs to Format & Expanded Bases of ITS ML20196L2911999-05-19019 May 1999 Forwards Responses to NRC 990315 RAI Concerning GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves A36791, Forwards Response to NRC 990510 RAI Re GL 96-06 with Respect to Analysis of Water Hammer & two-phase Flow Issues. Supporting Calculation Also Encl1999-05-17017 May 1999 Forwards Response to NRC 990510 RAI Re GL 96-06 with Respect to Analysis of Water Hammer & two-phase Flow Issues. Supporting Calculation Also Encl ULNRC-04034, Forwards Amerenues Risk Evaluation Summary & Provides Listing of Other Documents Which Have Been Previously Provided to Support Evaluation of Electrosleeves at High Temp Severe Accident Conditions1999-05-17017 May 1999 Forwards Amerenues Risk Evaluation Summary & Provides Listing of Other Documents Which Have Been Previously Provided to Support Evaluation of Electrosleeves at High Temp Severe Accident Conditions 05000483/LER-1998-003, Forwards LER 98-003-01 Re Inadvertent Actuation of ESFAS Due to 'A' SG High Level During Refuel 9.Rept Is Submitted to Report Change in C/A from That Reported in Original Rept1999-05-12012 May 1999 Forwards LER 98-003-01 Re Inadvertent Actuation of ESFAS Due to 'A' SG High Level During Refuel 9.Rept Is Submitted to Report Change in C/A from That Reported in Original Rept ML20206Q9551999-05-12012 May 1999 Responds to NRC Re Violations Noted in Insp Rept 50-483/99-04.Corrective Actions:Une Commits to Make Available for NRC Review,Action Plan Outlining Scope & Completion Dates of Project ULNRC-04027, Forwards Comments on Draft SE Re Proposed Conversion to Improved Tss.Copy of ITS & ITS Bases Will Be Provided by 990524,to Support Issuance of License Amend on or About 9905281999-05-0404 May 1999 Forwards Comments on Draft SE Re Proposed Conversion to Improved Tss.Copy of ITS & ITS Bases Will Be Provided by 990524,to Support Issuance of License Amend on or About 990528 ML20206E3211999-04-28028 April 1999 Forwards Special Rept 98-03 Re Inservice Insp of CP Sgs,Per Plant TS 4.4.5.5.b.Insp Was Performed in Apr 1998 During Plant Ninth Refueling Outage.Rept Is Being Resubmitted Due to Typos in Original Rept ML20206E5781999-04-23023 April 1999 Informs That R Schukai Is No Longer Employed with Amerenue & Info Sent Is No Longer Required.Name Should Be Removed from Mailing Lists.Mailing Label Used by Company Which May Assist in Matter,Submitted ULNRC-04018, Submits follow-up Items Re Proposed Conversion to ITS Sections 1.0,3.3,3.4,3.6,3.7 & 3.9.Suppl to Ltr Will Be Submitted at Later Date1999-04-21021 April 1999 Submits follow-up Items Re Proposed Conversion to ITS Sections 1.0,3.3,3.4,3.6,3.7 & 3.9.Suppl to Ltr Will Be Submitted at Later Date ML20205Q7751999-04-16016 April 1999 Forwards Special Rept 98-03 Concerning ISI of Callaway SGs Performed in Apr 1998 During Callaway Plants Ninth Ro. Rept Documents Final SG Insp Results ULNRC-04015, Forwards Cash Flow Projection & Certification to Satisfy Guarantee of Payment of Retrospective Premiums,Per 10CFR140.211999-04-15015 April 1999 Forwards Cash Flow Projection & Certification to Satisfy Guarantee of Payment of Retrospective Premiums,Per 10CFR140.21 ULNRC-04005, Forwards Proprietary & non-proprietary White Paper Entitled, Evaluation of Severe Accident Simulation, as Addl Info to Facilitate Approval of Requested Amend to Revise TS to Use Repair SG Tubes.Proprietary Info Withheld,Per 10CFR2.7901999-04-0707 April 1999 Forwards Proprietary & non-proprietary White Paper Entitled, Evaluation of Severe Accident Simulation, as Addl Info to Facilitate Approval of Requested Amend to Revise TS to Use Repair SG Tubes.Proprietary Info Withheld,Per 10CFR2.790 ULNRC-04004, Forwards Proprietary Thermal Stability Background Data Along with Time/Temp Graph Requested in 990402 Telcon with NRC & Contractor,Argonne Natl Lab.Proprietary Info Withheld1999-04-0707 April 1999 Forwards Proprietary Thermal Stability Background Data Along with Time/Temp Graph Requested in 990402 Telcon with NRC & Contractor,Argonne Natl Lab.Proprietary Info Withheld ULNRC-04007, Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6 & 3.7.Encl Includes mark-ups of ITS Sections 3.5,3.6 & 3.8.Suppl to Ltr Will Be Provided at Later Date1999-04-0707 April 1999 Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6 & 3.7.Encl Includes mark-ups of ITS Sections 3.5,3.6 & 3.8.Suppl to Ltr Will Be Provided at Later Date ULNRC-04000, Forwards Rept Re Present Level of Insurance & Sources of Insurance Applicable to Callaway Plant,Per 10CFR50.54(w)1999-04-0101 April 1999 Forwards Rept Re Present Level of Insurance & Sources of Insurance Applicable to Callaway Plant,Per 10CFR50.54(w) ULNRC-03998, Forwards Required Financial Info Re Decommissioning Callaway Nuclear Plant,Per 10CFR50.751999-03-30030 March 1999 Forwards Required Financial Info Re Decommissioning Callaway Nuclear Plant,Per 10CFR50.75 ML20205G2211999-03-25025 March 1999 Submits Rev 28A to Callaway Plant Physical Security Plan, Incorporating Addendum Re Security Sys Replacement Transition Plan,Per 10CFR50.54(p).Encl Withheld,Per 10CFR73.21 ML20205R5251999-03-25025 March 1999 Forwards Special Rept 98-03 Re Results of Tenth SG Tube Inservice Insp,Per Requirements of Plant TS 4.4.5.5.b.Insp Was Performed in Apr 1998 During Plant Ninth Refueling Outage ULNRC-03988, Requests Approval of Alternative Exam ISI-12A Per 10CFR50.55a(a)(3)(i) & (II) for 1989 Edition of ASME Section IX,IWA-5242(a) for Class I Bolted Connections Inside Bioshield for RFO 101999-03-19019 March 1999 Requests Approval of Alternative Exam ISI-12A Per 10CFR50.55a(a)(3)(i) & (II) for 1989 Edition of ASME Section IX,IWA-5242(a) for Class I Bolted Connections Inside Bioshield for RFO 10 ULNRC-03991, Forwards 1998 Annual Rept of Individual Monitoring Results, Per 10CFR20.2206.Rept Provided in Electronic Format on Diskette IAW Gudiance of Reg Guide 8.7.Without Diskette1999-03-19019 March 1999 Forwards 1998 Annual Rept of Individual Monitoring Results, Per 10CFR20.2206.Rept Provided in Electronic Format on Diskette IAW Gudiance of Reg Guide 8.7.Without Diskette ML20204F7211999-03-17017 March 1999 Forwards Amended Fitness for Duty Program Performance Data for Six Month Period Beginning Jul-Dec 1998 ML20204E1331999-03-17017 March 1999 Responds to NRC Re Violations Noted in Insp Rept 50-483/99-02 on 990208-12.Corrective Actions:Will Revise Security Plan to Increase Min Staffing by Three Armed Security Force Response Personnel Per Shift ML20207C3631999-03-12012 March 1999 Forwards Exam Matl & Associated QA Checklist for Written Exam to Support Plant RO Retake Exam Scheduled for 990423. Exam Matls Requested to Be Withheld from Public Disclosure Until After Exam Completion 05000483/LER-1998-001, Forwards LER 98-001-01,being Submitted to Clarify Scope of Original Reviews Performed for Corrective Action Number 3 in LER 98-001-00.Reviews Have Identified Case of Failure to Properly Establish Equipment Operability1999-03-10010 March 1999 Forwards LER 98-001-01,being Submitted to Clarify Scope of Original Reviews Performed for Corrective Action Number 3 in LER 98-001-00.Reviews Have Identified Case of Failure to Properly Establish Equipment Operability ULNRC-03979, Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6,3.7,3.8,3.9 & 5.0.Suppl to Ltr Dtd 970515,will Be Provided at Later Date1999-03-0909 March 1999 Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6,3.7,3.8,3.9 & 5.0.Suppl to Ltr Dtd 970515,will Be Provided at Later Date ULNRC-03975, Informs of No Reportable ECCS Evaluation Model Revs for Callaway During Time Period from Mar 1998 to Mar 1999,IAW 10CFR50.46.ECCS Evaluation Model Margin Assessment Encl1999-03-0505 March 1999 Informs of No Reportable ECCS Evaluation Model Revs for Callaway During Time Period from Mar 1998 to Mar 1999,IAW 10CFR50.46.ECCS Evaluation Model Margin Assessment Encl ULNRC-03971, Forwards Annual Personnel Exposure & Monitoring Rept for 1998, Per TS Sections 6.9.1.4 & 6.9.1.5.Rept Includes One Incident of Specific Activity Analysis of RCS in Which Limits of TS 3.4.8 Were Exceeded1999-02-26026 February 1999 Forwards Annual Personnel Exposure & Monitoring Rept for 1998, Per TS Sections 6.9.1.4 & 6.9.1.5.Rept Includes One Incident of Specific Activity Analysis of RCS in Which Limits of TS 3.4.8 Were Exceeded ML20207A4311999-02-17017 February 1999 Forwards semi-annual Fitness for Duty Program Performance Data Rept for Callaway Nuclear Plant for Period of 980701-981231 1999-09-15
[Table view] |
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Union EI:ctric one Ameten VIaza March 9,1999 INO$$I[ l St. Louis, MO 63166-6149 31 n t1 1222 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station PI-137 Washington, D. C. 20555-0001 ULNRC-03979 Gentlemen:
TAC NO. M98803 DOCKET NUMBER 50-483 CALLAWAY PLANT UNION ELECTRIC COMPANY FOLLOW-UP ITEMS RELATED TO THE b PROPOSED CONVERSION TO TIIE IMPROVED TECHMCAL Tjfggfgg SPECIFICATIONS SECTIONS 3.3. 3.4. 3.6. 3.7. 3.8. 3.9. AND 5.0
References:
- 1. ULNRC-03578 dated May 15,1997
- 2. ULNRC-03877 dated August 4,1998
- 3. ULNRC-03927 dated November 25,1998
- 4. ULNRC-03900 dated September 24,1998
- 5. ULNRC-03853 dated June 26,1998
- 6. ULNRC-03905 dated October 21,1998
- 7. ULNRC-03937 dated December 11,1998
- 8. ULNRC-03908 dated October 21,1998
- 9. ULNRC-03926 dated November 23,1998
- 10. ULNRC-03946 dated December 22,1998
- 11. ULNRC-03957 dated February 5,1999 Union Electric Company requested an amendment to the Callaway Facility Operating License (NPF-30) by incorporating changes to the Technical Specifications (TS) as provided in Reference 1. The NRC staff requested additional information regarding Section 3.1, " Reactivity Control Systems,"
Section 3.2, "Powcr Distribution Limits," Section 3.5, " Emergency Core Cooling Systems," Section 3.9, " Refueling Operations," and 4.0, " Design Features," which was provided in Reference 2. The NRC staff requested additional information regarding Section 3.3, " Instrumentation," which was provided in Reference 3. The NRC staff requested additional information regarding Section 3.4, " Reactor Coolant System," and Section 5.0, " Administrative Controls," which was provided in Reference 4. The NRC naff requested additional information regarding Section 3.6," Containment Systems," which was provided in Reference 5. The NRC staff requested additional information regarding Section 3.7, " Plant Systems," which was provided in Reference 6. In addition, the NRC staffrequested additional I information regarding Section 3.8, " Electrical Power Systems," which was provided in Reference 7. (
(
l The Attachments to this letter provide (1) additional information or supporting documentation not provided in the original RAI responses, (2) answers tGOGGa~ to follow-up questions, and (3) additional changes identified by the licensee for ITS Sections 3.3,3.4,3.6,3.7,3.8,3.9, and 5.0. Reference 8 provided the first follow-g031703799993o9 ~-
p ADOCK 050 93
f .
U. S. Nuclear Regulatory CCmmission March 9,1999 Page 2 up letter, affecting ITS Sections 3.1, 3.2, 3.4,3.5, and 5.0. Reference 9 provided the
- second follow-up letter, affecting ITS Sections 1.0,3.4,3.5,3.6,3.7, and 3.9.
l Reference 10 provided the third follow-up letter, affecting ITS Sections 1.0,3.1, 3.2,3.3,3.4,3.7,3.9, and 5.0. Reference 11 provided the fourth follow-up letter, affecting ITS Sections 1.0, 3.2, 3.3, 3.4, 3.6, 3.7, 3.8, 3.9, and 5.0.
This letter and its Attachments are not a supplement to Reference 1 and have not been reviewed by the Onsite Review Committee or Nuclear Safety Review Board. A supplement to Reference I will be provided at a later date.
, If you have any questions concerning this response, please contact us.
L L..d &
A Alan C. Passwater
/ Manager, Corporate Nuclear Services GGY/pir ;
i
I .
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STATE OF MISSOURI ) 1
) SS I l CITY OF ST. LOUIS )
David Shafer, of lawful age, being first duly sworn upon oath says that he is Supervising Engineer, Corporate Nuclear Services, Regulatory Operations for Union Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said company with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
By As-Al -
David Shafer '
Supervising Engineer, Regulatory Operations, i Corporate Nuclear Services I
SUBSCRIB D a sworn to before me this day of /7 /4ft' , 1999.
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PATRICIA L REYNOLDS NOTUi/ POUC-LTATE OF MISSOUfu u4. L 4 COUNTY MY COMMISWON EXPIRES DEC.22,2000 l
i cc: 'M. H. Fletcher Wfd Professional Nuclear Consulting, Inc.
19041 Raines Drive Derwood, MD 20855-2432 I' RegionalAdministratorWfA U.S. Nuclear Regulatory Commission Region IV :
l 611 Ryan Plaza Drive Suite 400 ,
Arlington, TX 76011-8064 Senior Resident Inspector W/d Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Mel Gray (2) H/fA Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1 White Flint, North, Mail Stop 13E16 11555 Rockville Pike Rockville, MD 20852-2738 Manager, Electric Department Missouri Public Service Commission P.O. Box 360 Jefferson City, MO 65102 Ron Kucera Department of. Natural Resources P.O. Box 176 Jefferson City, MO 65102 Denny Buschbaum W[A TU Electric P.O. Box 1002 !
Glen Rose, TX 76043 PatNugentW!d Pacific Gas & Electric Regulatory Services P.O. Box 56 Avila Beach, CA.93424 l
l
.S The item numbers are formatted as follows: [ Source][lTS Section]-[nnn]
Source = Q - NRC Question NR - NRC Follow-up Question CA- AmerenUE DC-PG&E WC - WCNOC CP - TU Electric TR - Traveler ITS ltem Number Applicability Enclosed _
1.0 Q 1.1-1. TSTF-205 WC NA 3.1 WC-3.1-001 (NEW) WC N-3.2 WC-3.2-002 (NEW) WC NA
~ 3.3 Q 3-LS-GEN, TSTF-135 WC NA 3.3 Q 2-02 (3.3) CA, t ; YLTS 3.3 Q 2-18 CA,WC YES 3.3 Q 2-37 WC NA l 3.3 O 3-01 WC NA 3.3 Q 7-13 CA, WC YES l 3.3 Q 3.3-04 CA YES !
3.3 Q 3.3-21 CA, WC YES l 3.3 O 2.3-30 WC NA l 3.3 Q 3.3-32 CA,WC YES j 3.3 Q 3.3-34 CA, DC, WC YES _
l 3.3 Q 3.3-55 CA,WC YES l 3.3 Q 3.3-80 CA, WC YES l 3.3 0 3.3-99 CA,WC YES I 3.3 Q 3.3-135 CA, WC YES I l 3.3 CA-3.3-024 (NEW) CA YES 3.3 CA-3.3-025 (NEW) CA YES 3.3 TR-3.3-007 DC NA !
i- 3.3 WC-3.3-020 (NEW) WC NA ,
3.3 WC-3.3-021 (NEW) WC NA l 3.3 WC-3.3-022 (NEW) CA, DC, WC YES 3.3 WC-3.3-023 (NEW) WC NA 3.3 WC-3.3-024 (NEW) WC i NA
I l
I 3.4 O 3.4.11-2, TSTF-288 CA, DC, WC YES l 3.4 Q 3.4.11-3. TSTF-113 CA, WC YES l
3.4 WC-3.4-011 WC NA l 3.6 O 3.6.1-6 CA,DC YES :
3.6 O 3.6.3-1 WC NA l 3.6 O 3.6.3-4 CA YES i 3.6 O 3.6.3-10 CA YES I 3.6 O 3.6.3-11 WC NA l 3.6 Q 3.6.3-17 CA YES CA, WC
)
3.6 Q 3.6.3-23 YES ,
3.6 Q 3.6.3-33 CA YES l l 3.6 Q 3.6.6-8 DC NA 3.7 O 3.7.16-3 CA, WC YES 3.7 Q 3.7.17.1-6 CA, WC YES 3.7 CA-3.7-005 CA YES 3.7 CA-3.7-010 (NEW) CA YES 3.7 CA-3.7-011 (NEW) CA YES 3.7 WC-3.7-009 (NEW) WC NA 3.7 WC-3.7-010 (NEW) WC NA 3.7 WC-3.7-011 (NEW) WC NA 3.8 Q 3.8.1-09 CW CA YES 3.8 Q 3.8.',-12 DC DC NA 3.8 Q 3.8.1-12 WC WC NA 3.8 Q 3.8.1-15 WG WC NA 3.8 Q 3.8.1-18 DC DC NA 3.8 Q 3.8.1-27 DC DC NA 3.8 O 3.8.1-29 DC DC NA 3.8 Q 3.8.1-33 DC DC NA 3.8 Q 3.8.2-04 CW CA YES 3.8 O 3.8.3-06 DC DC NA 3.8 O 3.8.4-08 WC NA 3.8 O 3.8.4-10 CA YES 3.8 O 3.8.4-17 WC NA 3.8 Q 3.8.4-18 CA YES 3.8 O 3.8.4-29 WC NA l 3.8 O 3.8.B-01.a CA YES 3.8 Q 3.8.B-01.g CA YES l
3 3.8 Q 3.8.B-01.j CA YES 3.8 Q 3.8.B-01.p CA YES 3.8 Q 3.8.B-04.r WC NA 3.8 CA-3.8-003 (NEW) CA YES 3.8 DC-3.8-ED DC NA 3.8 WC-3.8-007 (NEW) CA, WC YES 3.9 WC-3.lf-007 (NEW) CA, DC, WC YES 4.0 WC-4.0-ED (NEW) WC NA 5.0 Q 5.2-1, TSTF-258 CA YES 5.0 WC-5.0-007 (NEW) WC NA l
l 1
1 l
l
c ,
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 2-02-A (3.3) APPLICABILITY: CA, WC REQUEST: CTS ACTION b.1, Equation 2.2-1, and the values for Total Allowance (TA),
Z, and Sensor Error (S) are deleted, consistent with NUREG-1431 Rev.1.
Comment: Explain the LG classification for deleting CTS requirements. The staff position is that this change is less restrictive because limits (required operator actions) contained in the CTS are deleted and now given elsewhere in licensee controlled documents.
{WC, CW} The staff also notes this CN is a duplice'a - CN 2-03 A for LSSS changes. Additional CN 2-03A comments are provn .3 sith that CN in this table.
FLOG RESPONSE (original): New DOC 2-54-M has been written regarding elimination of ACTION b.1 in CTS 3.3.2. DOC 2-03-A in the 2.0 package has been revised to reference DOC 2-54-M in the 3.3 package.
FLOG RESPONSE (supplement): DOC 2 54-M is revised to refer to ACTION b.1 n the first sentence.
ATTACHED PAGES:
Attachment 9, CTS 3/4.3 - ITS 3.3 Enclosure 3A, page 25 (INSERT 3A-25 page 1 of 3) l i
- =- _ _ _
L
, INSERT 3A-25 (page 1 of 3)
Ah 2-49 -
Not used.
i' 2-50 LG 'The CTS [##] note of Table 3.3-3 is revised to move the $ J 7-43 l descriptive material related to the automatic blocking of the interlock to the ITS 3.3.2 Bases. Moving these details does not effect the Applicability or the Operability of the Function which will continue to protect the health and safety of the public.
2-51 e Not applicable to Callaway. See Conversion Comparison Q f.7 M Table (Enclosure 38).
2-52 -
Not applicable to Callaway. See Conversion Comparison g1/7.-f5.
Table (Enclosure 38).
2-53 LG in this Callaway-specific change, the tie breaker closure $ 7,7-2f discussion in ACTION 19 of CTS Table 3.3-3 is moved to s the LCO Bases for ITS 3.3.5 as one example of multiple channels inoperable on one bus. Moving this detail to the ITS Bases has no impact on the system attributes required for OPERABILITY. In addition, moving this detail to the Bases is acceptable since OPERABILITY requirements and supporting surveillances are retained in the ITS and
~
the moved information will be adequately controlled under the Bases Control Program of ITS Section 5.5.14. There will be no change to current plant practices nor any impact on safety. DOC 2-18-LS-31 contains the justification for extending the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> breaker closure allowance to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. _.
2-54 M Although C 2-02-A characterizes the deletion of d 3-O-A ACTION rom LCO 3.3.2 as adm_inistrative since the change is wnm.=niwith current piant practice, since thP{
trip setpoint adjustment is done for a majority of analog channels with the channel in trip and therefore declared inoperable (i.e., no different in effect than entering ACTION b.2), there could be scenarios where ACTION b.1 would present another attemative. For instance, since containment pressure High-3 has an installed bypass design feature, ACTION b 1 could allow trip setpoint adjustments in bypass. This would eliminate logging requirements for equipment out of service. Since this change is eliminating ACTION b.1 as an allowed recourse, this is a more restrictive change.
2-55 - Not applicable to Naway. See Conversion Comparison O 3-d~/
Table (Enclosure 6B). {p,3)
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 2-18 APPLICABILITY: CA, WC REQUEST: Current TS Table 3.3-3 ACTION Statement 19 is revised to reflect ITS 3.3.5 for the Loss of Power Functional Unit.
Comment: [OOS)- Reject. Proposed change extends CTS AOTs for 2,3, and 4 inoperable channels to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The CTS AOT changes are not evaluated. AOT extensions not consistent with ISTS loss of redundancy and loss of function actions and CTS are OOS. Adopt ISTS for loss of redundancy and loss of function for inoperable LOP actuation channels or translate CTS requirements into lTS format.
The NSHC discussion on entry into LCO 3.0.3 specifies this change "does involve any relaxation in the allowed outage time currently required by LCO 3.0,3 " Please clarify this statement. The staff notes that the NUREG gives a one hour repair AOT for loss of function conditions which is allowed based on the one hour in LCO 3.0.3 given that the LCO includes a LCO 3.0.3 equivalent shutdown requirement.
FLOG RESPONSE (original): The last comment under Comment Number Q 1-18-LS-7 is aise applicable to this DOC.
As discussed during meetings with NRC staff on September 15 and 16,1998, ITS 3.3.5 Required Action B.1 has been revised in response to Comment Number Q 3.3-99 to immediately declare the associated load shedder and emergency load sequencer (LSELS) inoperable. The extended AOT for multiple inoperable channels on one bus in MODES 1-4 is evaluated in DOC 2-18-LS-31 and is consistent with Vogtle's approved ITS. We agree that this is an out of scope change, as identified in Attachment 3 of the original ITS submittal. However, we feel that this change is justified and the attached pages include revisions to DOC 2-18-LS-31 and to LS-31 to further support this change.
The NSHC LS-31 discussion referenced in the second paragraph above is based on a comparison of shutdown time requirements in CTS LCO 3.0.3 vs. ITS LCO 3.3.5. Since ACTION 19 of current TS Table 3.3-3 for Functional Units 8.a and 8.b does not address the inoperability of more than one channel, the failure of multiple channels would result in entering current LCO 3.0.3 which requires that the plant be brought to MODE 3 in 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> and MODE 5 in 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />. ITS 3.3.5 Conditions C and D also require that the plant be brought to MODE 3 in 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> and MC-DE 5 in 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />. While ITS 3.3.5 Condition C explicitly allows one hour for restoration, ITS 3.3.5 Required Action D.1 (i.e., be in MODE 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />) effectively eliminates the one hour for action initiation present in CTS LCO 3.0.3. Under the current TS, if LCO 3.3.2 were restored in the first hour the plant would exit LCO 3.0.3. Therefore, this is not seen as a relaxation; however, DOC 2-18-LS-31 and NSHC LS-31 have been revised to more correctly characterize this sentence to say that this Condition has the same shutdown track time in both the CTS and ITS.
FLOG RESPONSE (supplement): Additional changes have been made to DOC 2-18-LS-31 and NSHC LS-31. See the attached pages for Comment Number O 3.3-99.
ATTACHED PAGES:
None
l-ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 7-13 APPLICABILITY: CA, WC .
t e
REQUEST: This item was identified during the licensee /NRC meeting on August 11, l
1998. The NRC requested a DOC be initiated to identify either moving portions of CTS i
SR 4.3.3.5.2 concerning operating each actuated component from the ASP or deletion of .
. the requirement. '!
I I
l FLOG RESPONSE (original): DOC 7-13 LS-44 was initicted. The DOC states:
l " CTS SR 4.3.3.5.2 requires the auxiliary shutdown panel (ASP) controls be demonstrated OPERABLE at least once per 18 months by operating each )
actuated component from the ASP. The proposed change revises CTS SR l
4.3.3.5.2 to delete the phrase by operating each actuated component from the i ASP." The OPERABILITY of the ASP controls ensures there is sufficient information available on selected unit parameters to place and maintain the unit in MODE 3 should the control room become inaccessible. CTS SR 4.3.3.5.2 verifies that the ASP controls perform the intended function. The CTS requirement to opera!e each actuated component is overly restrictive since the specific components associated with the ASP are verified OPERABLE by other specifications. For example, FSAR Section 7.4.3.1.1 identifies the ,
automatic / manual control for each power operated atmospheric dump valve as !
an ASP control. ITS SR 3.7.4.1 verifies that the atmospheric dump valve is l OPERABLE by performance of one complete cycle of each valve. Operation of the equipment from the ASP is not necessary. The surveillance can be satisfied by' performance of a continuity check. Performance of this surveillance in conjunction with the performance of other required surveillances on equipment associated with the ASP will ensure that if the control room becomes inaccessible, the plant can be placed and maintained in MODE 3."
FLOG RESPONSE (supplement): Based on comments from the NRC reviewer on
' February 4,1999, DOC 7-13-LS-44 and NSHC LS-44 have been revised per the attached.
ATTACHED PAGES:
Attachment 9, CTS 3/4.3 - ITS 3.3 Enclosure 3A, page 29 and INSERT 3A-298 Enclosure 4, page 82 (new)
T l
CHANGE
^'
-. NUMBER HSBC. DESCRIPTION MIM 3A--39A
'.-J 7 12 A New Note excludes neutron detectors from CHANNEL CALIBRATION consistent with current TS Table 4.31 47-/M g gg,, g Functional Unit 6. Note 4 and with improved TS SR 3.3.4.3. i MEW 3'A-M8
/801 A This change consistent with NUREG-1431 Rev.1. revises
" Channel" and " Instrument" to " Function."
d? 7-jg 8 02 -
Not used. 1 8 03 A This change revises current TS Table [3.310] to clarify the number of channels required to be operable. This is )
an administrative change which deletes the " Minimum )
Channels Operable" column [and revises the "[ Total] No. of Channels" column to be the " Required Channels" column].
The required actions are now based on one channel inoperable or two channels inoperable, rather than "less than the Total Number" or "less than Minimum Number." )
This change is consistent with NUREG 1431 Rev.1. j i
8 04 LS 17 Consistent with NUREG 1431 Rev.1 (ITS 3.3.3 Required j Actions C.1. E.1, and G.1). this change deletes the i requirement to initiate an alternate means of monitoring within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when two channels of Containment Radiation Level [or RVLIS] are inoperable as specified in current TS [3.3.3.6 Action c].
8 05 A In conjunction with CN 8 03 A. this change rearranges the ACTION Statements for the single channel Functions (i.e. .
SG Water Level -
Wide Range and AFM Flow Rate). No change in A0T is requeste 6Mhire C C @ DED f .rNJ4er 3A-19L) $ E 3"2- 0 ,
8 06 LG Specific equipment ID numbers are moved to the ITS Bases. I 8 07 -
Not applicable to Callaway. See Conversion Comparison Table (Enclosure 3B).
8 08 LS 27 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 3B).
~
3 09 - l-G M aed. *2WEGR7~ 3% ~1W 8 10 -
Not used. l 8 11 LS 30 Not applicable to Callaway. I See Conversion Comparison g p,_jj Table (Enclosure 38).
f, ]l - + +
f--//
~
+ a DESCRIPTION OF CHANGES TO CURRENT TS 29 5/15/97
l
, INSERT 3A-29A
[ 7-/2M Since neutron flux is one of the required channels and the detectors are normally excluded from CHANNEL CAllBRATIONS in other specifications, this Note applies to the SR Frequency in CTS Table 4.3 6. Neutron detectors are one type of sensor that can no. be adjusted per the definition of CHANNEL CALIBRATION. As discussed in the ITS SR 3.3.1.11 Bases, the CHANNEL CA,LIBRATION for the source range detectors consists of obtaining integral bias curves, evaluating those curves, and comparing the curves to the manufacturer's data. This Note in ITS SR 3.3.4.3 is consisten+ with other CTS requirements for calibrating channels containing neutron detectors. This change is considered an administrative clarification of existing requirements.
INSERT 3A-298 f) %/3 CTS SR 4.3.3.5.2 requires the auxiliary shutdown panel (ASP) controls be demonstrated OPERABLE at least once per 18 months by operating each actuated component from the ASP. The proposed change revises CTS SR 4.3.3.5.2 to delete the phrase "by operating each actuated component from the ASP." The OPERABILITY of the ASP
~~
controls ensures there is sufficient information available on selected unit parameters to place and maintain the unit in MODE 3 should tne control room become inaccessible.
CTS SR 4.3.3.5.2 verifies that the ASP controls perform the intended function. The CTS ;
. requirement to operate each actuated component is overly restrictive since the specific j components associated with the ASP are verified OPERABLE by other specifications.
For example, FSAR Sectic,n 7.4.3.1.1 identifies the automatic / manual control for each power operated atmospheric dump valve as an ASP control. ITS SR 3.7.4.1 verifies that the atmospheric dump valve is OPERABLE by performance of one complete cycle of each valve. Operation of the equipment from the ASP is not necessary. The surveillance l can be satisfied by performance of a continuity chec Performance of this surveillance I in conjunction with the performance of other require rveillances on equipment associated with the ASP will ensure that if the control com becomes inaccessible, the )
plant can be placed and maintained in MODE 3.
(er M M O'b' * !
I l
l l
INSERT LS-44 h 7~M
'h IV. SPECIFIC NO SIGNIFICANT HAZARDS CONSIDERATIONS NSHC LS-44 10 CFR 50.92 EVALUATION FOR TECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE REQUIREMENTS WITHIN THE TECHNICAL SPECIFICATIONS CTS SR 4.3.3.5.2 requires the auxiliary shutdown panel (ASP) controls be demonstrated OPERABLE at least once per 18 months by operating each actuated component from the ASP. The proposed change revises CTS SR 4.3.3.5.2 to delete the phrase "by operating each actuated component from the ASP."If temporary evacuation of the control room is regul' .1 because of some abnormal condition, the operators can establish and maintain the plant in a hot standby condition from outside the control room.
The OPERABILITY of the ASP controls ensures there is sufficient information available on selected unit parameters to place and maintain the unit in MODE 3 should the control room become inaccessible. CTS SR 4.3.3.5.2 verifies that the ASP controls perform the intended function. The CTS requirement to operate each actuated component is overly restrictive since the specific components associated with the ASP are verified OPERABLE by other specifications. For example, FSAR Section 7.4.3.1.1 identifies the automatic / manual control for each power operated atmospheric dump valve as an ASP g control. ITS SR 3.7.4.1 verifies that the atmospheric dump valve is OPERABLE by performance of one complete cycle of each valve. Operation of the equipment from the ASP is not necessary. The surveillance can be satisfied by performance of a continuiti chec erformafice of this surve'IIIi' n in conjunction with the performance of other requ surveillances on equipment as ciated with the ASP will ensure that if the contro om becomes inaccessible, th plant can be placed and maintained in MODE 2.
p3 Z*rTSR 3.2.4;3 This propose cag een evaluated and it has been determined that it involves no significant hazards consideration. This determination has been performed in accordance with the criteria set forth in 10 CFR 50.92(c) as quoted below:
7
'The Commission may make a finaldeterminatio.1, pursuant to the procedures in 50.91, that a proposed amendment to an operating license for a facility licensed under 50.21 (b) or 50.22 or for a testing facility involves no significant hazards consideration, if operation of the facilityin accordance with the proposed amendment would not:
- 1. Invoin a significant increase in the probability or consequences of an accident previously evaluated; or
- 2. Create the possibility of a new or different kind of accident from any accident previously evaluated; or P2
ADDITIONAL INFORMATION COVER SHEET l ADDITIONAL INFORMATION NO: O 3.3-04 APPLICABILITY: CA REQUEST: This change represents the Callaway plant design as it relates to the SG Water Level-Low Low Environmental Allowance Modifier (EAM) and Trip Time Delay i (TTD) circuitry. ITS Table 3.3.1-1 and Table 3.3.2-1 entries and the associated Required i Actions have been enhanced to remove the redundancy in the current TS and add l shutdown actions when inoperable channels aren't tripped per their Completion Time. I Comment: Beyond Scope - because plant unique actions are modified as stated in the DOC.. . " Enhancements to remove CTS redundancy in the CTS and added shutdown actions."[ sic) Revise ITS Actions E (as applied to function 14), and X to adopt CTS requirements without modification. [see 1-19-LS 8)
Provide a separate DOC for changes made to CTS Action 7 for Functions 13.a and 13.b. CTS Action 7 is translated into ITS Condition W. Condition W applies only to ITS 14.c functions for Vessel AT Power-1, and Power-2 which are 1 equivalent to CTS Function 13.c. !
l Based on 8/14/98 meeting (CW) to provide 163 M and 162 LS. -
CTS Action 35 provides actions for a single inoperable timer. ITS Action N allows one or more timers to be inoperable. This change is neither noted norjustified in ;
the CTS markup. ;
l l
FLOG RESPONSE (original): DOC 1-19-LS-8 has nothing to do with the SG Water Level Low-Low EAM/TTD trip functions at Callaway. That DOC concerns only those reactor trip functions interlocked with permissive P-7. DOC 1-42-M (DOC 2-14-M for corresponding ESFAS changes) addresses the changes to Actions 7,11, and 13 in )
current TS Table 3.3-1 to require entering MODE 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> rather than in 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> (as would be the case with an LCO 3.0.3 entry).
Contrary to the Reference 4 meeting minutes, there should be no need to provide a new "1-62-LS" change and a new "163-M" change only to move the TTD timer Action Statement 7 to the Functional Unit to which that Action has always applied. Moving this j Action Statement number in CTS Table 3.3-1 is administrative; no change to current )
practices is involved. New DOC 1-62-A has been written to cover the movement of ;
Action 7 from Functional Units 13.a and 13.b in current TS Table 3.3-1 to Functional Unit i 13.c in that table, with a detailed discussion as to why this change is considered to be administrative in nature. Actions 7 and 11 now apply to Functional Unit 13.c since they l both involve tripping the Vessel AT (Power-1, Power-2) channels. New DOC 1-62-A also discusses the corresponding ESFAS changes which mirror the RTS changes.
JFD 3.3-04 has been ,avised to reflect DOCS 1-42-M (DOC 2-14-M for ESFAS) and 1 A.
l
.- .- -- . - ~
In ITS 3.3.1, Condition E corresponds to Action 6 (which has been rewritten as Action )
2.1 in the conversion submittal) for current TS Functional Unit 13.a. Condition E has j been revised in response to Comment Number 3.3-40 (setpoint adjustment deleted from Note).
Condition W corresponds to Actions 7 (added per new DOC 1-62-A) and 11 for current TS Functional Unit 13.c. The format and wording presentation of Condition W and Required Action W.1 are retained for clarity given the discussion in new DOC 1-62-A.
Several of the RTS Conditions identify the affected Function and Required Action W.1 must be clear as what channel (s) to trip to remove the time delay in the event of an inoperable timer.
Condition X corresponds to Action 13 for current T3 Functional Unit 13.b. Required Action X.1 has been retained and DOC 1-46-A has been revised to provide more ,
discussion. FSAR Figure 7.2-1 sheet 7A is attached to illustrate the EAM logic. I Condition Y corresponds to Action 11 for current TS Functional Unit 13.d. Required Action Y.1 is reworded to delete the identity of the affected channel since that identity is already established in the Condition.
In ITS 3.3.2, ESFAS Required Action O.1 has been revised to reflect the change to RTS Required Action Y.1.
The last paragraph of the comment was answered in the September meetings, as reflected by Reference 6.
FLOG RESPONSE (supplement): Based on comments received from the NRC reviewer on February 16,1999, the changes to CTS 3.3.1 ACTION 13 and CTS 3.3.2 ACTION 36 that were previously evaluated under DOC 1-46-A are now evaluated under DOC 1-46-M. These ACTIONS have been revised to handle the SG water level low-low (normal containment environment) channels the same as the SG water level low-low (adverse containment environment) channels, i.e., with one channel inoperable place it in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Corresponding changes to Enclosures 2,3A,3B, ;
SA, and 5B have been made. '
I ATTACHED PAGES:
Attachment 3, Table of Changes not within the Scope of Full Conversion to the ISTS, page 10 Attachment 9, CTS 3/4.3 - ITS 3.3 l Enclosure 2, pages 3/4 3-6(a), insert 3/4 3-6(a)-1,3/4 3-21(b), insert 3/4 3-21(b)
Enclosure 3A, pages 14,15, insert 3A-15 Enclosure 3B, page 10 Enclosure SA, pages 3.3-10,3.3-19,3.3-20, 3.3-31,3.3-32, 3.3-33, insert 3.3-42,3.3-43, 3.3-44, and 3.3-45 Enclosure 58, pages B 3.3-30, B 3.3-48, B 3.3-58, B 3.3-59, B 3.3-60, B 3.3-74, insert B 3.3-110 (page 2 of 2),8 3.3-113, B 3.3-114, B 3.3-128, B 3.3-136, B 3.3-137, B 3.3-138, and B 3.3-150 I
- .- - =. --.
Enclosure 6A, page 8 Enclosure 68, page 10 i
. .