Letter Sequence Other |
---|
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
|
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
[Table View] |
|
---|
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] |
Text
Union Electric One Ameren Plaza 1C31 Chouteau Avenue i i , i PO Box 66149 I
y
'j -
' SL louis, MO 63166-6149 April 7,1999 I' -
3wram i
1 U.S. Nuclear Regulatory Commission l l ATTN: Document Control Desk Mail Station PI-137 Washington, D.C. 20555-0001 ULNRC-04007 i Gentlemen: -TAC NO. M98803 l
DOCKET NUMBER 50-483 CALLAWAY PLANT
. gg, UNION ELECTRIC COMPANY l FOLLOW-UP ITEMS RELATED TO THE PROPOSED CONVERSION TO THE l NN IMPROVED TECPNICAL SPECIFICATIONS SECTIONS 3.3. 3.4. 3.6. AND 3.7
- #E Refere- x 1. ULNRC-03578 dated May is,1997 l
- 2. ULNRC-03927 dated November 25,1998 l
3 TENRC-03900 dated September 24,1998
- 4. ULNRC-03853 dated June 26,1998
- 5. ULNRC-03905 dated October 21,1998
- 6. ULNRC-03908 dated October 21,1998 l 7. ULNRC-03926 dated November 23,1998
- 8. ULNRC-03946 dated December 22,1998 l
- 9. ULNRC-03957 dated Febmary 5,1999
- 10. ULNRC 03979 dated March 9,1999 Union Electric Company requested an amendment to the Callaway Facility Operating License (NPF-30) by incorporating changes to the Tecimical Specifications (TS) as provided in Reference 1. The NRC staff reguested addthnal information regarding Section 3.3, "Instmmentation," which was provided in Reference 2. The NRC staff requested additional information ./
regarding Section 3.4, "Reaam Coolant System," and Section 5.0," Administrative /
Controls," which was provided in Reference 3. The NRC staff reguested additional information regarding Section 3.6, " Containment Systems," which was provided in Reference 4. In addition, the NRC staff reguested additional information regarding Section 3.7, " Plant Systems," which was provided in Reference 5.
The Attachments to this letter provide (1) additional information or fol o supporting documentation not provided in the original RAI responses, (2) answers to follow-up questions, and (3) additional changes identified by the licensee for ITS Sections 3.3,3.4,3.6, and 3.7. Additional sections are also affected since Comment Number 3.3-99 includes mark-ups ofITS Section 3.8 Bases pages, Comment Number CA-3.7-ED includes mark-ups ofITS Section 4.0 pages, and Comment Number CA-3.7-012 includes mark-ups of Bases pages for ITS Sections 3.5 and 3.6.
- 4 O h f \ 't 9904140131 990407 PDR ADOCK 05000483 P PDR 3 e subsidiary of Amoren Corporation
i 1
U.S. Nuclear Regulatcy Commission R E April 7,1999 Page 2 Reference 6 provided the first follow-up letter, affecting ITS Sections 3.1, 3.2,3.4, 3.5, and 5.0. Reference 7 provided the second follow-up letter, affecting ITS Sections 1.0,3.4,3.5,3.6,3.7, and 3.9. Reference 8 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 9 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. Reference 10 provided the fifth follow-up letter, affecting ITS Sections 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.
Sincerely, AL :AM1 Alan C[Passw#ater Manager, Corporate Nuclear Services ACP/pir
, -ij
4 t
i
.1 STATE OF MISSOURI )
-) SS 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 execuned 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 L_ .: o _1 1 . 1 . -
David Shafer '
Supervising Engineer, Regulatory Operations, Corporate Nuclear Services SUBSCRIBED and sworn to before me this day of (l44EY , 1999.
I
,,...n e n e ,,,, // # / /// $
L ..R..
... t<
i
!= ese*%
- ~ k appy M /
'3TE
PATRICIA L REYNOLDS
. If0TA51/,OAINTATE OF M1880UM UT. o D COL"ITY
-' MY C0thsbl0M EXhAES DEC.22, NW ~
f
cc: M. H. Fletcher Professional Nuclear Consulting, Inc.
19041 Raines Drive Derwood, MD 20855-2432 Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive Suite 400 Arlington, TX 76011-8064 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Mel Gray (2)
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 TU Electric P.O. Box 1002 Glen Rose, TX 76043 Pat Nugent Pacific Gas & Electric z Regulatory Services 1 P.O. Box 56 Avila Beach, CA 93424
)
_____-_____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 Item Number Applicability Enclosed 3.3 0 3-08 DC NA 3.3 Q 3.3-21 CA YES 3.3 0 3.3-32 CA YES 3.3 Q 3.3-37 DC NA 3.3 Q 3.3-43 CA,DC YES 3.3 0 3.3-46 DC NA 3.3 Q 3.3-54 DC NA 3.3 Q 3.3-66 DC NA 3.3 0 3.3-71 DC NA 3.3 0 3.3-77 DC NA 3.3 O 3.3-82 DC NA 3.3 0 3.3-99 CA YES 3.3 Q 3.3-104 DC NA 3.3 CA-3.3-002 CA YES 3.3 CA-3.3-006 CA,DC YES 3.3 CA-3.3-024 CA YES
_3J CA-3.3-025 CA YES 3.3 _
CA-3.3 026 CA YES 3.3 CA-3.3-027 CA YES 3.3 DC-3.3-004 DC NA 3.3 DC-3.3-006 (NEW) DC NA 3.3 DC-3.3-007 (NEW) DC NA 3.3 DC-3.3-008 (NEW) DC NA 3.3 DC-3.3-009 (NEW) DC NA 3.3 DC-3.3-ED DC NA 3.3 DC-3.3-ED1 (NEW) DC NA 3.3 DC-ALL-005 (3.3 changes only) DC NA 3.4 Q 3.4.11-3 _
CA YES
3.6 O 3.6.3-10 DC NA 3.6 Q 3.6.3 CA YES 3.6 Q 3.6.3-39 DC NA 3.6 Q 3.6.6-19 DC NA 3.6 CA-3.6-ED2 (NEW) CA YES 3.7 CA-3.7-ED CA YES 3.7 CA-3.7-012 CA YES 3.8 Q 3.8.1-33 DC NA 3.9 DC-ALL-001 (3.9 changes only) DC NA 1
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.3-21 APPLICABILITY: CA REQUEST: ITS 3.3.3 was revised to reflect current TS 3.3.3.6 containment isolation valve position (and Notes) and condensate storage tank level were deleted. [ Combined the power and source range neutron flux entries into a single neutron flux entry.]
Consolidated the thermocouple / core cooling detection system entries. Changed number of required channels for RCS temperature to 2 for both hot and cold leg temperature.
Changed containment pressure wide range to containment pressure normal range and added refueling water storage tank level, steam line press Jre, and SG water level (Narrow Range) functions as these are current TS requirements. Changed the required number of channels for SG water level (Wide Range) and AFW flow rate from 2 per SG to 1 per SG and added corresponcling mtes to Conditions A and C.
Comment: (1) ITS includes thermocouples as PAM instrument functions without specifying the number required to be operable. Provide a revised table entry for function 15. Include the appropriate discussion of change.
(2) Provide a table footnote to specify the need for the operable instruments to be in the same coolant loop. Provide a Bases discussion of the proposed footnote.
{WC}
(3) Correct the table entry making it based on each core quadrant as a table function. The Bases Actions in WC already specify the quadrant basis. CW may need to make conforming Bases changes. {WC & CW}.
(4) Revise ITS Conditions A & C Notes pertaining to AFW and SG water level inoperable channels. Two instrumented SGs are required to be operable to conduct a plant shutdown. Thus, the LCO is 1 channel each of AFW and wide range level per SG The staff does not credit AFW as diverse to Level which means one inoperable AFW or Level channel in a SG results in loss of the PAM monitoring function for that SG Therefore, Conditions are entered when less than 2 SGs have both AFW and wide range level channel operable. Condition A for AFW and wide range level functions should allow a 30 day Completion Time for one or more inoperable AFW or Level channels in one, two or three SGs.
Condition C for AFW or wide range level functions should allow a 7 day Completion for one or more inoperable AFW or Level channels in each SG FLOG RESPONSE (original): (1) This comment is applicable to Wolf Creek only. The ITS markup has been corrected to reflect the Required Channels as "2(*)/ core quadrant" consistent with the CTS.
(2) This comment is applicable to Wolf Creek and Callaway. It is assumed that this comment is referring to Table 3.3.3-1, Functions 2 and 3 (RCS Hot and Cold Leg Temperature (Wide Range)) and the deletion of the "per loop" in the Required Channels column. The "per loop" was deleted based on the plant design of one hot leg temperature indicator (wide range) and one cold !eg temperature indicator (wide range)
in RCS loops 1 and 2. Attached are pages from USAR/FSAR Table 7A-3 (Data Sheets 2.1 and 2.2) that indicate the plant design provisions. This change is consistent with CTS Table 3.3-10.
(3) See the response to item 1 for correcting ITS Table 3.3.3-1 for Wolf Creek. The Wolf Creek and Callaway Bases both state: "When the Required Channels in Table 3.3.3-1 are specified on a per SG or per core quadrant basis, then the Condition may be entered separately for each SG or core quadrant, as appropriate." No changes to the ITS Bases are necessary.
(4) There is one wide range water level indicator for each steam generator (AE-LI-0501 through -0504 in the main control room). Diverse indications are available from four narrow range level indicators for each SG when on scale and one AFW flow indicator per SG as discussed in USAR/FSAR Table 7A-3, Data Sheet 4.1. Reactor coolant pressure and reactor coolant temperature indications are also diverse variables from the aspect that they can be used to determine whether adequate core cooling is provided in the absence of wide range levelindication on a steam generator. Additional heat sink status diversity is also provided by three steamline pressure indicators per loop. There is one AFW flow rate indicator for each SG (AL-FI-0001 A through -004A in the main control room). Although not required for Regulatory Guide 1.97 Category 2 variables, diverse indicatir,5 are available from one wide range level indicator and four narrow range level indic.cors per SG. As discussed in Table 7A-3, Data Sheet 5.1, each of these four flow indicators is powered by a different separation group. Since only two of four SGs are required to establish a heat sink for the RCS, flow indication to at least two intact SGs is assured even if a single failure is assumed. Section 22 of the Safety Evaluation Report, NUREG-0830 for Callaway and NUREG-0881 for Wolf Creek, specifically accepted the response to NUREG-0737 Item ll.E.1.2 Part 2 for AFW flow rate indication and the CTS, as originally issued, did not "AND" wide range level with AFW flow rate as discussed in the comment. Table 7A-3, Data Sheets 4.1 and 5.1 have been attached to this response for information. The proposed ITS mark-ups maintain the CTS 3.3.3.6 requirements.
(5) Item 5 is a new item applicable only to Wolf Creek that was discussed during the Section 3.3 meeting held the week of August 11,1998. This item is to revise Table 3.3.3-1 Function 1, Power Range Neutron Flux and Function 2, Source Range Neutron Flux, into one Function, Neutron Flux. Neutron Flux indication is provided to verify reactor shutdown over the full range of flux that may occur post-accident. One channel of the 5
Gamma-Metric neutron flux monitoring system provides source range (0.1 to 10 cps) and wide range (10*to 200% power)in the control room. The second channel provides source and wide range indication at the auxiliary shutdown panel, as well as a two-pen indicating recorder (SE-NIR-0061) for both source and wide ranges in the control room.
Neutron flux is used for accident diagnosis, verification of subcriticality, and diagnosis of positive reactivity insertion. The Neutron Flux function was added to CTS 3/4.3.3.6 by Amendment No. 89. Therefore, changing the Function to Neutron Flux is consistent with the plant design and the CTS.
FLOG RESPONSE (supplement): As discussed with the NRC reviewer on February 17, 1999, ITS 3.3.3 and associated Bases are revised. Conditions A and C are revised to delete specific reference to the SG Water Level (Wide Range) and AFW Flow Rate Functions. Table 3.3.3-1 is revised for these two Functions to indicate that the Required Channels is 4 (i.e., one per SG). Additiondly, in Table 3.3.3-1, the Core Exit
1 Temperature Functions are restored instead of specifying the Themocouple/ Core i Cooling Detection System.
FLOG RESPONSE (supplement): The attached ITS 3.3.3 Bases changes are made in response to comments received from the NRC reviewer on March 12,1999.
ATTACHED PAGES: , CTS 3/4.3 - ITS 3.3 Enclosure SB, pages B 3.3-170 and B 3.3-173 (insert SR 3.3.3.2) 1