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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
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June 16, 1997 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk i Mail Station P1-137 Washington, DC 20555-0001 i
Gentlemen:
ULRNC-3602 l
l Callaway Plant Docket Number 50-483 Callaway Nuclear Plant Inservice Testing Program Update This letter transmits Revision 18 of the Callaway Nuclear Plant Inservice Testing (IST) Program. IST Program l updates have been made via Revisions 15a, 16, and 17 which
! are included in Revision 18. In accordance with the l guidance provided in NUREG 1482 " Guidelines for Inservice Testing at Nuclear Power Plants," this revision is being 1 provided to reflect major changes to the IST Program.
Attachment 1 is a brief description of the changes, and
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Attachment 2 contains a copy of Revision 18 of the IST Program.
l If you have any questions concerning this l submittal, please contact us.
1 Vr uly y rs
-1 Cha les D. Naslund I
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Attachments I l
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1 9706250104 970616 llllllllllllllllllllfllll ll PDR ADOCK 05000483 P PDR 1
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l Revision 15a Summary of Channes to the IST Program
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l Engineering evaluations have been perfonned for these changes and no Unreviewed Safety j Question exists as a result of this revision. The following table explains all changes by component. ;
1 Components Affected Description of Chance Justification for channe ENHV0001, ENHV0006, Components were changed from An engineering evaluation determined that ENHV0007. ENHV0012, " passive" to " active" several containment spray valves have an active ENV0002, ENV0003, safety function in the closed direction. These ENV0004, ENV0008, components were already receiving the code '
ENV0009, and ENV0010 required testing for active components and therefore only needed to be administratively changed in the Inservice Test Program component list to be active.
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i 1 Attachment I
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- g a e Revision 16 Summary of Changes to the IST Program Engineering evaluations have been performed for these changes and no Unreviewed Safety Question exists as a result of this revision. The following table explains all changes by component.
Components Affected Description of Chance Justification for chance PAL 01 A, PAL 0lB, and PALO2 Changed the test frequency of A recent change to the Technical Specifications the AFW pumps from monthly revised the periodicity from 31 days to 92 days to quarterly. Reference OL on a staggexd test basis. Changing the Amendment 108. frequency is in accordance with Technical Specifications and ASME/ ANSI OMa-1988 Pan 6, Section 5.1 PEF 01B, ABPV0002, Changed the drawing This is a clarification to more accurately reflect ABPV0003, ABHV0011, coordinates. the drawing coordinates. There are no changes ABHV0012, BB8948C, to the testing of the components. This change is BB8010A, BB80108, administrative.
BB8010C, BBHV8157B, BBV0474, BBV0476, BBV0479, BBV0480, BBV8001B, BBV8002B, BGV0605, ECV0083, ECV0084, EGHV0054, EJHV0025, EMHV8923 A, EPHV8950A, EPHV8950D, GSHV0004, HBHV7150, SJHV0018, SJHV0019, and SJHV0005 n/a Added a "SV" code for Solenoid "SV" was being used for solenoid valve in Valves to "VLV Type" in Revision 15 and needed to be defined. This is an Section 2.1. administrative change that does not affect valve testing.
ABHV00ll, ABHV0014, Corrected the Actuator Type The actuator type ns incorrectly identified.
ABHV0017, ABHV0020, from AO (Air Operated) to HO This is an administrative change that does not AEFV0039, AEFV0040, (Hydraulic Operated). affect va!ve testing.
AEFV0041, and AEFV0042 ALHV0005, ALHV0006, Changed the safety position This is a change to make this column consistent ALHV0007, AL.HV0008, from "C/O" to "O/C" with the rest of the IST program. This is an ALHV0009, ALHV0010, administrative change that does not affect vahe ALHV0011,and ALHV0012 testing.
ALHV0036, BB8378A, Revised the description to This is a change to make the description BB8379B, BGHV8112, components to match the consistent with the rest of the IST program. This 1 BNHV8813, EFHV0023, description in the Master is an administrative change that does not afTect I EFHV0024, EFHV0025, Equipment List. valve testing.
EFHV0026, EFHV0060, EGHV0060, EJ89698, EJFCV0611, EJHV8804B, EJHV881IB, EM8815, EMHV8801 A, EMHV8801B, i EMHV8803 A, EMHV8803B, EMHV8923 A, and EMHV8843 2
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Components Affected Descrintion of Change Justification for change ,
BBV0ll8, BBV0148, The listed valve size was changed The listed valve size was incorrect. This is an I BBV0178, BBV0208, in accordance with plant administrative change that does not affect valve
- BBV0122, BBV0152, drawings. testing. )
i BBVO182, BBV0212, 1 ECV0095, ECV0096, EMHV8923 A, and EMHV8923B BGLCV0459 and BGLCV0460
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Added valves to the IST Program A recent evaluation determined that these and added a" COLD valves have an active safety function to close.
SHUTDOWN JUSTIFICATION" Adding these valves to the IST Program is a "BG-09" conservative change as it increases testing.
l BGV0605 and BGV0606 Corrected the description to This is a correction to a typographical error. I change "UPSTEAM" to This is an administrative change that does not l
" UPSTREAM" afTect valve testing.
BGV0645 Added to the IST Program. The IST program did not indicate that the valve was being tested. However, OSP-BG V001C tests this valve on a quarterly frequency (ST-04054) for closure. This is an administrative change that does not alTect valve testing.
BLilV8047 Changed "SO" to "AO" in the The actuator type was inconectly identified.
- "ACF " column. This is an administrative change that does not i
affect valve testing.
i BMHV0019, BMHV0020, Added "FF/Q" to the " TEST The IST program did not indicate that the salve BMHV0021, and BMHV0022 PERF/FREQ." column. was being tested to fail closed. However, this testing was being performed on a quanctly basis in accordance with OSP-BM-V000l(ST-00061). This is an administrative change that does not affect valve testing.
ECHV0011 and ECHV0012 Changed the "VLV TYPE" The valve type was incorrectly identified. This column from "BT" to "BF". is a correction to a typographical error that does not affect valve testing.
EGHV0072, EGHV0073, Corrected an error in the "VLV The valve type was incorrectly identified. This EGHV0074, EGHV0075, and TYPE" column from "GT" to is a correction to a typographical error that does FCHV0312 "G B" not afTect valve testing.
EJHV0023, EJHV0024, Changed the valve function to The safety classification, test performed, EJHV0025, and EJHV0026 " PASSIVE", The following frequency and valve type for these valves were changes to Tests Performed and incorrect. This is an administrative change that frequency were made: Deleted does not affect valve testing.
"FS/Q" and added "LJ/RF" for components EJHV0023 and EJHV0025, and added "PI/RF" to EJHV0024 and EJHV0026.
Changed Valve Type from "GB" to "GT" for EJHV0023, EJHV0024 and EJHV0025.
(Note: Tests Perf/Freq was subsequently revised again in Revision 17.)
EJHV8701A A "/" was placed between "LT This is a correction to a typographical error.
RF" located in the " TESTS This is an administrative change that does not PERF/FREQ" column. affect valve testing.
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Components Affected Descrintion of Chance Justification for chance EMHV8801A Changed the valve category The valve Category was incorrectly identified.
from "A,C" to "B" The correct category is "B" This is an administrative change that does not affect valve testing. Correct testing was performed.
GTHZ0004, GTHZ0005, Corrected the Actuator Type The Actuator Type was incorrectly identified.
GTHZ0006, GTHZ0007, from "SO"(Solenoid Operated) This is an administrative change that does not GTHZ0008, GTHZ0009, to "AO" (Air Operated). affect valve testing GTHZ0010, GTHZO0ll, and GTHZ0012 GTHZ0006, GTHZ0007, Changed the " Active or Passive" The fields were simplified to make them easier to GTHZ0008, and GTHZ0009 field and added Note 1. understand. This is an administrative change that does not affect valve testing.
JEV0086 Changed "SFTY POS" from "0" This was a typographical error. The capital (zero) to "O", letter 'O' is the correct entry C r this field. This is a correction that does not afTect valve testing.
KBV0001 and KBV0002 Added to the IST Program. These are passive containment isolation valves and have been tested by procedure OSP-KB-LLO98. This change is administrative and does not affect valve testing.
KCHV0253 Added "PI/RF" to the " TESTS The Tests Performed list was incomplete. The PERF/FREQ." column. fNote: Leak Test and Position Indication Test are being Tests Perf/Freq was performed on a refueling frequency by procedure subsequently revised again in OSP-KC-LLO67. This is an administrative Revision 17.) change that does not affect valve testing.
LFHV0105, LFHV0106, and Changed "G A" to "GT" in the These were typographical errors This is an LFFV0095 "VLV TYPE" column. administrative change that does not affect valve testing.
LFFV0096, SJHV0005, Changed "GL" to "GB" in the These were typographical errors. This is an SJHV0006, SJHV0127, "VLV TYPE" column. administrative change that does not afTect valve SJHV0128, SJHV0129, testing.
SJHV0130, SJHV0131, and SJHV0132 n/a Revised the labeling format of This is only a clarification to make the IST Relief Requests / Cold Shutdown Program document more consistent. This is an Justifications / Refueling administrative change that does not affect valve Justifications to make them testing.
administratively consistent.
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Revision 17 Summary of Channes to the IST Program Engineering evaluations have been perfonned for these changes and no Unreviewed Safety Question exists as a result of this revision. The following table explains all changes by component.
Components Affected Description of Change Justification for change J n/a Sectica 2.1, page 2, the codes These codes are more consistent by indicating the "2" (for 2 years) and "J" (for required test frequency rather than indicating the Appendix J frequencies) were actual test frequency. This is an administrative added for frequency. clarification.- i n/a Section 2.2, Column " TESTS This was modified to support the changes above.
PERF/FREQ.", changed all This is an administrative change to be consistent l
l Position Indications to "PI/2" with allowed Code specified frequencies.
and changed all Appendix J leak rate valve tests to "LJ/J" BBV0ll8, BBV0148, Valves were changed from an An engineering evaluation determined that these BBV0178 and BBV0208 " Active" closed Safety Position valves have a passive open safety function.
to a " Passive" open Safety 1 Position and removed the l "FS/RF" test requirement.
BGV0135, KAV0039, Added "C" for the "VLV CAT." Even though these valves are passive. the passive KAV0648, KAV0649, check valves will be identified as categon 'C'. This KAV0650, KAV0651, and is an administrative change. This has no impact to KCV0478 the testing of the valves.
n/a Revised the " CATEGORY" This is an administrative change. This has no l I
section of Refuel Justification impact on the testing of the valves.
BB-04, Refuel Justification EM-03, and Cold Shutdown Justification BG-06 to reflect the Valve Category in the corresponding table.
EGLV0001 and EGLV0002 Added to the IST program. An engineering evaluation determined that these valves have a passive safety function in the closed position. Therefore, a position indication test is required. Adding these valves to the IST Program is a conservative change as it adds more testing EGHV0058, EGHV0059, Valves safety position were An engineering evaluation determined that these EGHV0060, EGHV0061, changed from "O/C" to "C" valves only hase the actise function to close.
and EGHV0062 5
i ao t e Revisinn 18 Summary of Changes to the IST Program 4
Engineering evaluations have been performed for these changes and no Unreviewed Safety Question exists as a result of this revision. The following table explains all changes by component.
1 Components Affected Description of Change Justification for chance ABV0085; ABV0087 The safety position of these These valves are normally locked in the open components was revised from position in order to ensure steam supplier are "O/C" to "C", available for the TDAFP. In the event of a SGTR ,
these valves must be closed to stop ofTsite release paths. As these are manual isolation valves without remote position indication there are no testing requirements in the open (passive) position. Thus.
, the safety function column for these valves has been changed to "C"(active position). Verification that these valves can be closed will continue to be done
- during refueling outages as stated in Refueling
- Justification AB-03.
BGV0135 Changed the SFTY POS column This component has been determined to have an
, from "C" to "O/C" Added active safety function in the partial open position in l "PS/RF" to the TEST PERF/FREQ order for it to relieve pressure between j column. Changed the active or BGHV8100/8112 in the event they become isolated passive column to add " ACTIVE" and pressure between these containment isolation Added BG02 to the RR OR TST valves increases. In the normally closed position I DEF JUST column. this valve serves a passive function for containment isolation. Per Table 1 of OM 10 this valve requires i valve seat leak rate testing (Category A passive i
valve test per parag aph 4.2.2) and exercise testing (Categog C active check valve per OM-10 paragraph 4.3.2). Refueling Justification BG-02 was revised to test the open function of this valve on a extended test frequency. Since this valve does not i have remote position indication it does not require l position indication testing per OM 10 paragraph l 4.1. l BN8717 This valve has beesi added to the This valve prevents RHR inventory from being l
IST program as a passive diverted back to the RWST. During Modes 1,2,3,4 component with remote position this valve is maintained locked closed (padlocked).
indication. During Modes 5 and 6 this valve can be opened for refueling pool inventory changes. Due to the safet) l significance of this flowpath, this valve has been provided with ESFAS status panel indication j (remote position indication). Per OM 10 Table 1 Category B passive valves require position indication testing per paragraph 4.1.
BNV00ll This valve has been added to the This component is the RWST isolation salve. The )
IST program as a passive RWST is the borated water supply to support ECCS component with remote position injection. This valve ensures the ECCS pumps hase indication. a suction flowpath from the RWST. Due to the safety significance of this flowpath, this salve has been provided with ESFAS status panel indication (remote position indication). Per OM-10 Table 1 Category B passive valves require position indication testing per paragraph 4.1.
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Comnonents Affected Descrintion of Chance Justincation for change EGHV0071 & These valves have been added to EGHV0071 and '26 are isolation valves in the EGHV0126 the IST program as passive CCW flowpath to the containment CCW loads.
components with remote position EGHV0071 is normally maintained in the open indication. position as part of the primary CCW flowpath to containment. EGHVol26 is an isolation valve m the bypass line around EGHV0071. EGHVol26 can be opened to maintain CCW flow to containment in the event EGHV0071 is closed. These vahes are considered passive components. Per OM 10 Table I i Category B passive valves require position l indication testing per paragraph 4.1.
EJFCV0618 & These valves have been added to These components are isolation valves on the RHR EJFCV0619 the IST program as passive heat exc' inger bypass line. During the normal components with remote position ECCS lineup these valves are maintained in the indication. closed position. This ensmes that RHR flow is directed through the RHR heat exchanger for maximum RCS cooling for the recirculation phase of RHR operation. These valves are only taken out ,
l of the closed position for testing or RHR flow / temperature control during cold shutdown or l refueling outages. These valves are considered passive components. Per OM-10. Table 1, Category B passive valves require position indication testmg j per paragraph 4.1.
EJHCV0606 & These valves have been added to These components are isolation vahes on the outlet EJHCV0607 the IST program as passive of the RHR heat exchangers. During the normal components with remote position ECCS lineup these valves are maintained in the indication. open position to ensure RHR injection flow to the RCS following a large break LOCA. These sahes are only taken out of the full open posmon for testing or RHR llow/ temperature control during cold shutdown or refueling outages These valves are considered passive components. Per OM-10. Table 1, Category B passive valves require position indication testing per paragraph 4.1.
EJHV0014 & EJHV0015 These valves have been added to These components can be opened to direct a portion the IST program as passive of RHR flow to the nuclear sampling system for components with remote position testing. These valves are assumed closed during all indication. other modes of operation for RHR. These valves are considered passive. Per OM-lo. Table 1. Category B passive valves require position indication testing per paragraph 4.1.
EMHV8889A,B,C,& D These valves have been added to These components are isolation valves in the SIS the IST program as passive test header. They are typically maintained in the components with remote position closed position with air isolated to preclude indication. inadvertent opening . They are normally only opened for RCS pressure isolation leak rate testmg (BB8949A.B,C &D). These vahes are mstalled at a seismic boundary which will ensure that the assumed SI pump flow is directed to the RCS in the event of a line break downstream of these vahes These sahes are considered passh e Per OM In.
Table 1, Category B passive valves require position indication testing per paragraph 41.
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Comnonents Affected Descrintion of Change Justification for change EMHV8924 This valve has been added to EMHV8924 is an isolation valve between the RHR the IST program as passive pumps and SIP /CCP's. This flowpath is used when it component with remote becomes necessary to supply the suction of the CCP's position indication. and SIP's from RHR. Isolation of this valve while in Moder 1,2,3 places the plant in Technical Specification 3.03. Ne to the safety significance of this flawpath the valve handw heel is locked in the open position with the associated supply breaker locked in the open position.
This valve is considered passive. Per OM-10, Table 1.
Category B passive valves require position indication testing per paragraph 4.1.
EMV0006 The ACTIVE or PASSIVE This check valve is a containment isolation valve in the classification for this valve SI Accumulator fill line. Although this penetration is was changed to " ACTIVE" typically isolated by EMHV8888, it is being considered In addition, "FS/RF" was an active valve since this flowpath is routinely used added to the TESTS during normal plant operation. Justification EM-08 was PERF/FREQ column along developed to extend the required testing to refueling with refuelingjustification outages. As an active Category A.C check vahe OM-lu EM-08. This change was requires a leak test per paragraph 4.2.2 and an exercise identified while reviewing test per paragraphs 4.2. I and 4 3.2. Since this valve is changes to EPV0046 which is not equipped with remote position indication n is exempt a similar valve. from position indication test requirements.
EMHV8882 This valve has been added to EMHV8882 is an isolation valve in the SIS test header.
the IST program as a passive it is typically maintained in the closed position.
component with remote EMHV8882 is normally only opened for RCS pressure position indication. isolation leak rate testing (BBV0001,22,40 & $9).
EMHV8882 is installed at a seismic boundary which will ensure that the assumed high head injection flow is directed to the RCS in the event of a line break downstream of this valve. EMHV8882 is considered passive. Per OM 10, Table 1 Category B passne sahes require position indication testing per paragraph 41 EPHV8808A/D Revised the TESTS This change is in accordance with RFR 17044 A.
PERF/FREQ. and SFTY POS EPHV8808A/D are normally open valves with elecincal columns such that testing in power removed. These sah es hase a safety position in the open direction is indicated the open direction (passive function) These valves still as a PASSIVE function. have a safety function in the closed direction-EPHV8808A/D will require position indication testing m both directiens but will only requ e ntroke time testmg in the closed direction.
EPHV8875A,B,C & D These valves have been added These components are isolation salves in the nitrogen EPHV8878A,B,C & D to the IST program as passive supply lines and borated water supply lines to the S1 components with remote Accumulators. These vahes are opened mtermittently position indication. during normal plant operation to adjust the SI Accumulators level and/or pressure. Typically these valves are maintained closed. Since these valves are e!'a located at scismic boundaries they arc assumed to maintain SI Accumulator operability in the esent of a liac break upstream of these valves. These valves are considered passive Per OM-10, Table I, Category B )
passive valves require position indication testing per paragraph 4.1.
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Components Affected Description of Change Justification for change
. EPHV8877A,B,C & D These valves have been added to These components are isolation valves in the SIS j theist program as passive test header. They are typically maintained in the components with remote position closed position and only opened for RCS pressure indication. isolation valve leak rate testing (EP8956A,B,C &
! D). These valves are also installed at a seismic i boundary which will ensure St Accumulator inventory is directed to the RCS in the event of a j line break downstream of these valves. These t components are considered passive. Per OM-10.
- Table 1, Category B passive valves require position i indication testing per paragraph 4.1.
- EPHV8879A,B,C & D These valves have been added to These components are isolation valves in the SIS the IST program as a passive test header. They are typically maintained in the j j component with remote position closed position with supply air isolated and are only )
j indication. opened following outages for RCS pressure isolation l
! valve leak rate testing (BB8948A.B.C & D). These i i
valves are also installed at a seismic boundary w hich j will ensure SI Accumulator /ECCS inventory is i
! directed to the RCS in the event of a line break j- downstream of these valves. These components are 4
considered passive. Per OM-10, Table 1. Category i B passive valves require position indication testing per paragraph 4.1. j EPV0046 The ACTIVE or PASSIVE This check valve is a containment isolation valve m l classification for this valve was the nitrogen supply line. Although this penetration ;
changed to" ACTIVE" In is typically isolated by EPHV8880, it is considered I addition,"FS/RF" was added to an active valve since this flowpath is routinely used the TESTS PERF/FREQ column during normal plant operation. Justification EP-06 along with refuelingjustification was developed to extend the required testing to EP-06. refueling outages. As an active Category A C check valve, OM 10 requires a leak test per paragraph 4.2.2 and an exercise test per paragraphs 4.2.1 and 4.3.2. Since this valve is not equipped with remote position indication it is exempt from position indication test requirements.
GSHV0030 & GSHV0035 Valves were added to the IST These valves are required to open to allow samphng program as active Category B of containment atmosphere post accident. These valves. valves are also required to maintain the mlegnty of the hydrogen analyz.crs sample lines by isolauon of tlie non seismic piping downstream. Per OM-10 Category B active valves are subject to quaner13 exercise testing per paragraph 4.2.1 and position indication testing per paragraph 4.1 every 2 years These valves are considered to have open and closed active safety functions 9
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