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MONTHYEARML20211C3651999-08-17017 August 1999 Forwards Rev 25 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program, Which Includes Reformatting of Manual & Addl Changes as Noted in Attached Summary of Changes Project stage: Other 1999-08-17
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F8231999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of Catawba Nuclear Station.Based on Review,Nrc Did Not Identify Any New Areas That Warranted More than Core Insp Program Over Next Five Months.Historical Listing of Issues,Encl ML20217H0041999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217F1301999-10-0707 October 1999 Forwards Rev 1 to Request for Relief 99-03 from Requirements of ASME B&PV Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting (Vg) Sys ML20212J3011999-10-0101 October 1999 Forwards Exemption from Certain Requirements of 10CFR54.17(c) Re Schedule for Submitting Application for Operating License Renewal.Se Also Encl ML20217K2651999-10-0101 October 1999 Forwards Retake Exams Repts 50-413/99-302 & 50-414/99-302 on 990921-23.Two of Three ROs & One SRO Who Received Administrative Section of Exam Passed Retake Exam, Representing 75 Percent Pass Rate 05000414/LER-1999-004, Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments1999-09-27027 September 1999 Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments 05000413/LER-1999-015, Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept1999-09-27027 September 1999 Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept ML20217A7911999-09-24024 September 1999 Forwards Insp Repts 50-413/99-05 & 50-414/99-05 on 990718- 0828 at Catawba Facility.Nine NCVs Identified Involving Inadequate Corrective Actions Associated with Degraded Svc Water Supply Piping to Auxiliary Feedwater Sys ML20212E6471999-09-24024 September 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for Catawba NPP & 990615.Informs That NRC Reviewed Response for Catawba & Concluded That All Requested Info Provided.Considers GL 98-01 to Be Closed for Catawba ML20212F0941999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals for Cns,Units 1 & 2 ML20212M2001999-09-20020 September 1999 Confirms 990913 Telcon Between M Purser & R Carroll Re Management Meeting to Be Conducted on 991026 in Atlanta,Ga to Discuss Operator Licensing Issues 05000414/LER-1999-005, Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments1999-09-20020 September 1999 Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments ML20212D5321999-09-15015 September 1999 Informs That Duke Energy Corp Agrees to Restrict Max Fuel Rod Average Burnup to 60,000 Mwd/Mtu,In Order to Support NRC Final Approval & Issuance of Requested Amend ML20212B4641999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for Catawba Nuclear Station,Units 1 & 2 ML20212A4131999-09-14014 September 1999 Informs That TR DPC-NE-2009P Submitted in 990817 Affidavit, Marked Proprietary,Will Be Withheld from Public Disclosure, Pursuant to 10CFR2.709(b) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20212M1931999-09-13013 September 1999 Refers to 990909 Meeting Conducted at Region II Office Re Presentation of Licensee self-assessment of Catawba Nuclear Station Performance.List of Attendees & Licensee Presentation Handout Encl ML20212A3751999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementation Code Case for Duration of Insp Interval ML20212A5191999-09-0808 September 1999 Requests NRC Approval for Relief from Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,App VI,VI-2430(c) & 2440(b).Approval of 99-GO-002 Is Requested by 000301 05000413/LER-1999-014, Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment1999-09-0101 September 1999 Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment 05000414/LER-1999-003, Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev1999-08-31031 August 1999 Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev 0 of LER ML20211H1741999-08-30030 August 1999 Forwards Comments on Catawba Nuclear Station Units 1 & 2 & McGuire Nuclear Station,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid.Ltr Dtd 990107,rept ATI-98-012-T005 & Partial marked-up Rept WCAP-14995 Encl ML20211M4451999-08-30030 August 1999 Forwards Summary of Util Conclusions Re Outstanding Compliance Issue Re Staff Interpretation of TS SR 3.0.1,per Insp Repts 50-369/99-03 & 50-370/99-03,as Discussed with NRC During 990618 Meeting 05000413/LER-1999-013, Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER1999-08-25025 August 1999 Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER ML20211M8191999-08-25025 August 1999 Confirms 990825 Telcon Between G Gilbert & R Carroll Re Mgt Meeting to Be Held on 990909 in Atlanta,Ga,To Allow Licensee to Present self-assessment of Catawba Nuclear Station Performance ML20211A9641999-08-20020 August 1999 Forwards SE Authorizing Licensee 990118 Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section XI for Plant,Units 2 ML20211C1191999-08-18018 August 1999 Forwards ISI Rept Unit 1 Catawba 1999 RFO 11, Providing Results of ISI Effort Associated with End of Cycle 11 ML20211B9471999-08-18018 August 1999 Forwards Request for Relief 99-02,associated with Limited Exam Results for Welds Which Were Inspected During Unit 1 End of Cycle 11 RFO ML20211C3651999-08-17017 August 1999 Forwards Rev 25 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program, Which Includes Reformatting of Manual & Addl Changes as Noted in Attached Summary of Changes ML20211F2971999-08-17017 August 1999 Forwards non-proprietary & Proprietary Updated Pages for DPC-NE-2009,submitted 980722.Pages Modify Fuel Design & thermal-hydraulic Analysis Sections of DPC-NE-2009. Proprietary Page 2-4 Withheld,Per 10CFR2.790 05000413/LER-1999-011, Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment1999-08-16016 August 1999 Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment ML20211B1121999-08-16016 August 1999 Forwards Topical Rept DPC-NE-2012, Dynamic Rod Worth Measurement Using Casmo/Simulate, Describing Results of Six Drwm Benchmark Cycles at Catawba & McGuire & Discusses Qualification to Use Drwm at Catawba & McGuire ML20210V0321999-08-13013 August 1999 Forwards Insp Repts 50-413/99-04 & 50-414/99-04 on 990606- 0717.Six Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20210S2751999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl ML20210Q3751999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr as Listed,Thirty Days Before Exam Date,In Order to Register Individuals for Exam ML20210N9521999-08-0404 August 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual.Documents Constitutes Chapter 16 of Ufsar.With List of Effective Pages IR 05000413/19980131999-08-0202 August 1999 Discusses Integrated Insp Repts 50-413/98-13,50-414/98-13, 50-413/98-16,50-414/98-16 & NRC Special Repts 50/413/99-11 & 50-414/99-11 Conducted Between Aug 1998 & May 1999.Six Violations Occurred,Based on OI Investigation & Insp ML20210M6411999-07-29029 July 1999 Forwards Request for Relief 99-03 from Requirements of ASME Boiler & Pressure Vessel Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting Air (Vg) Sys 05000413/LER-1999-010, Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units1999-07-22022 July 1999 Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units IR 05000413/19990101999-07-22022 July 1999 Discusses Insp Rept 50-413/99-10 & 50-414/99-10 on 990314- 0424 & Forwards Notice of Violation Re Failure to Comply with TS 3.7.13,when Misalignment of Two Electrical Breakers Rendered SSS Inoperable from 981216-29 ML20217G5241999-07-20020 July 1999 Forwards Exam Repts 50-413/99-301 & 50-414/99-301 on 990524- 27,0603,07-10 & 16.Of Fourteen SRO & RO Applicants Who Received Written Exams & Operating Tests,Eight Applicants Passed & Six Failed Exam 05000413/LER-1999-009, Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept1999-07-19019 July 1999 Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept 05000414/LER-1999-001, Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed1999-07-15015 July 1999 Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed ML20209H4431999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for May 1999 on Unit Shutdowns Also Encl ML20210A5771999-07-14014 July 1999 Forwards Revsied Catawba Nuclear Station Selected Licensee Commitments Manual, Per 10CFR50.71(e),changing Sections 16.7-5,16.8-5,16.9-1,16.9-3,16.9-5 & 16.11-7.Manual Constitute Chapter 16 of UFSAR ML20216D3941999-07-14014 July 1999 Forwards Revs to Catawba Nuclear Station Selected Licensee Commitments Manual NUREG-1431, Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation1999-07-0909 July 1999 Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196L0371999-07-0808 July 1999 Approves Requested Schedule Change of Current two-year Requalification Examinations to non-outage dates.Two-year Cycle Will Start on 991001 & Will End on 020930 05000413/LER-1999-008, Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach1999-07-0808 July 1999 Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach ML20196J9001999-07-0606 July 1999 Informs That 990520 Submittal of Rept DPC-NE-3004-PA,Rev 1, Mass & Energy Release & Containment Response Methodology, Marked Proprietary Will Be Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 IR 05000413/19990031999-07-0101 July 1999 Discusses Insp Repts 50-413/99-03 & 50-414/99-03 Completed on 990605 & Transmitted by Ltr .Results of Delibrations for Violation Re Discovery of Potentially More Limiting Single Failure Affecting SGTS Analysis Provided 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217H0041999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217F1301999-10-0707 October 1999 Forwards Rev 1 to Request for Relief 99-03 from Requirements of ASME B&PV Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting (Vg) Sys 05000414/LER-1999-004, Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments1999-09-27027 September 1999 Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments 05000413/LER-1999-015, Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept1999-09-27027 September 1999 Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept 05000414/LER-1999-005, Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments1999-09-20020 September 1999 Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments ML20212D5321999-09-15015 September 1999 Informs That Duke Energy Corp Agrees to Restrict Max Fuel Rod Average Burnup to 60,000 Mwd/Mtu,In Order to Support NRC Final Approval & Issuance of Requested Amend ML20212B4641999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for Catawba Nuclear Station,Units 1 & 2 ML20212A5191999-09-0808 September 1999 Requests NRC Approval for Relief from Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,App VI,VI-2430(c) & 2440(b).Approval of 99-GO-002 Is Requested by 000301 05000413/LER-1999-014, Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment1999-09-0101 September 1999 Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment 05000414/LER-1999-003, Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev1999-08-31031 August 1999 Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev 0 of LER ML20211H1741999-08-30030 August 1999 Forwards Comments on Catawba Nuclear Station Units 1 & 2 & McGuire Nuclear Station,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid.Ltr Dtd 990107,rept ATI-98-012-T005 & Partial marked-up Rept WCAP-14995 Encl ML20211M4451999-08-30030 August 1999 Forwards Summary of Util Conclusions Re Outstanding Compliance Issue Re Staff Interpretation of TS SR 3.0.1,per Insp Repts 50-369/99-03 & 50-370/99-03,as Discussed with NRC During 990618 Meeting 05000413/LER-1999-013, Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER1999-08-25025 August 1999 Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER ML20211B9471999-08-18018 August 1999 Forwards Request for Relief 99-02,associated with Limited Exam Results for Welds Which Were Inspected During Unit 1 End of Cycle 11 RFO ML20211C1191999-08-18018 August 1999 Forwards ISI Rept Unit 1 Catawba 1999 RFO 11, Providing Results of ISI Effort Associated with End of Cycle 11 ML20211C3651999-08-17017 August 1999 Forwards Rev 25 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program, Which Includes Reformatting of Manual & Addl Changes as Noted in Attached Summary of Changes ML20211F2971999-08-17017 August 1999 Forwards non-proprietary & Proprietary Updated Pages for DPC-NE-2009,submitted 980722.Pages Modify Fuel Design & thermal-hydraulic Analysis Sections of DPC-NE-2009. Proprietary Page 2-4 Withheld,Per 10CFR2.790 05000413/LER-1999-011, Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment1999-08-16016 August 1999 Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment ML20211B1121999-08-16016 August 1999 Forwards Topical Rept DPC-NE-2012, Dynamic Rod Worth Measurement Using Casmo/Simulate, Describing Results of Six Drwm Benchmark Cycles at Catawba & McGuire & Discusses Qualification to Use Drwm at Catawba & McGuire ML20210S2751999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl ML20210N9521999-08-0404 August 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual.Documents Constitutes Chapter 16 of Ufsar.With List of Effective Pages ML20210M6411999-07-29029 July 1999 Forwards Request for Relief 99-03 from Requirements of ASME Boiler & Pressure Vessel Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting Air (Vg) Sys 05000413/LER-1999-010, Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units1999-07-22022 July 1999 Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units 05000413/LER-1999-009, Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept1999-07-19019 July 1999 Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept 05000414/LER-1999-001, Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed1999-07-15015 July 1999 Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed ML20216D3941999-07-14014 July 1999 Forwards Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20209H4431999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for May 1999 on Unit Shutdowns Also Encl ML20210A5771999-07-14014 July 1999 Forwards Revsied Catawba Nuclear Station Selected Licensee Commitments Manual, Per 10CFR50.71(e),changing Sections 16.7-5,16.8-5,16.9-1,16.9-3,16.9-5 & 16.11-7.Manual Constitute Chapter 16 of UFSAR 05000413/LER-1999-008, Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach1999-07-0808 July 1999 Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach ML20196G7461999-06-22022 June 1999 Requests Exemption from Requirements of 10CFR54.17(c) That Application for Renewed Operating License Not Be Submitted to NRC Earlier than 20 Yrs Before Expiration of Operating License Currently in Effect ML20196E9541999-06-18018 June 1999 Forwards SG Tube Insp Conducted During Unit 1 End of Cycle 11 Refueling Outage.Attachments 1,2,3 & 4 Identify Tubes with Imperfections in SGs A,B,C & D,Respectively ML20195K4571999-06-14014 June 1999 Forwards MORs for May 1999 & Revised MORs for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20195J1691999-06-10010 June 1999 Forwards Written Documentation of Background & Technical Info Supporting Catawba Unit 1,notice of Enforcement Discretion Request Re TS 3.5.2 (ECCS-Operating),TS 3.7.12 (Auxiliary Bldg Filtered Ventilation Exhaust Sys) ML20217G5771999-06-0909 June 1999 Forwards Post Exam Comments & Supporting Reference Matls for Written Exams Administered at Catawba Nuclear Station on 990603 05000414/LER-1999-002, Forwards Abstract of LER 99-002-00 Re Forced Shutdown of Plant as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Final LER Will Be Submitted No Later than 9907081999-06-0303 June 1999 Forwards Abstract of LER 99-002-00 Re Forced Shutdown of Plant as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Final LER Will Be Submitted No Later than 990708 ML20207F2381999-06-0101 June 1999 Forwards Copy of Catawba Nuclear Station Units 1 & 2 1998 10CFR50.59 Rept, for NRC Files ML20195J1131999-05-26026 May 1999 Requests Approval to Change Cycle Dates for Two Year Requalification Training Program Required by 10CFR55.59,to Improve Scheduling of Requalification Exams to non-outage Periods 05000413/LER-1999-007, Forwards LER 99-007-00,re Operation Prohibited by TS 3.4.7. Commitments Identified in LER Are Listed in Planned Corrective Actions Section1999-05-26026 May 1999 Forwards LER 99-007-00,re Operation Prohibited by TS 3.4.7. Commitments Identified in LER Are Listed in Planned Corrective Actions Section ML20195B4751999-05-24024 May 1999 Forwards Rev 7 to UFSAR Chapter 2 & Chapter 3 from 1998 UFSAR for Catawba Nuclear Station.List of Instructions on Insertion Encl ML20196L1851999-05-20020 May 1999 Forwards Proprietary & non-proprietary Version of Rev 1 to TR DPC-NE-3004, Mass & Energy Release & Containment Response Methodology, Consisting of Finer Nodalization of Ice Condenser Region.Proprietary Info Withheld ML20196L1791999-05-20020 May 1999 Communicates Util Licensing Position Re Inoperable Snubbers. Licensee Has Determined That Structure of ITS Has Resulted in Certain Confusion Re Treatment of Inoperable Snubbers 05000413/LER-1997-009, Forwards LER 97-009-02, Unanalyzed Postulated Single Failure Affecting SG Tube Rupture Analysis, Suppl Revises Planned C/A Described in Suppl 1 to Ler.Current Status of C/As & Addl C/As Planned,Provided in Rept1999-05-17017 May 1999 Forwards LER 97-009-02, Unanalyzed Postulated Single Failure Affecting SG Tube Rupture Analysis, Suppl Revises Planned C/A Described in Suppl 1 to Ler.Current Status of C/As & Addl C/As Planned,Provided in Rept ML20206T4481999-05-13013 May 1999 Forwards Rev 3 to Topical Rept DPC-NE-3002-A, UFSAR Chapter 15 Sys Transient Analysis Methodology, IAW Guidance Contained in NUREG-0390 ML20206R1721999-05-13013 May 1999 Forwards Monthly Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 & Revised Monthly Operating Repts for Mar 1999 ML20206T0281999-05-12012 May 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual. Document Constitutes Chapter 16 of UFSAR 05000413/LER-1999-006, Forwards LER 99-006-00,re CR Ventilation Sys Inoperability. Root Cause & Corrective Actions for Occurence Are Being Finalized & Will Be Reported in Supplement Rept on 9906071999-05-10010 May 1999 Forwards LER 99-006-00,re CR Ventilation Sys Inoperability. Root Cause & Corrective Actions for Occurence Are Being Finalized & Will Be Reported in Supplement Rept on 990607 ML20206N8201999-05-10010 May 1999 Forwards Revs 15 & 16 to Catawba Unit 1 Cycle 12 COLR, Per TS 5.6.5.Rev 15 Updates Limits for New Catawba 1 Cycle 12 Reload Core & Rev 16 Revises Values Re Min Boron Concentrations for Rwst,Cla & SFP ML20206J4431999-05-0303 May 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual, Per 10CFR50.71(e).Document Constitutes Chapter 16 of UFSAR ML20206D2141999-04-29029 April 1999 Forwards 1998 Annual Radioactive Effluent Release Rept for Catawba Nuclear Station,Units 1 & 2, Per Plant TS 5.6.3. Rept Contains Listed Documents ML20206E4101999-04-26026 April 1999 Forwards Four Copies of Rev 9 Todpc Nuclear Security & Contingency Plan,Per 10CFR50.54(p)(2).Changes Do Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 1999-09-08
[Table view] |
Text
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.< !~N' Duke Power i,
Catawba Nudrar Station U, "
4800 Concord Road i York, SC 29745
,
g , (803) 831-3426 Mx
(
I August 17, 1999
{
U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk '
Washington, D.C. 20555
Subject:
Duke Energy Corporation Catawba Nuclear Station Unit 1 and 2 Docket No.: 50-413, 414 Inservice Testing (IST) Program for Pumps and Valves - Manual Update TAC MA6285 and MA6286 Per the requirement of 10 CFR 50.55a(f) (5) (i) , Revision 25 of the Catawba Nuclear Station Inservice Testing (IST)
Program Manual is enclosed. The changes include a reformatting of the manual and additional changes as noted I in-the attached Summary of Changes. The enclosed manual ;
will replace any previously transmitted revisions of the IST l Program. The following attachments are provided for this revision:
- 1. Summary of Changes !
- 2. CNS ASME IST Program Revision 25 !
Please direct any questions concerning this change to Martha Purser at (803 31-4015.
Sinc re ,
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G. R. Peterson )1 k(()k Attachment 99082b0$24'990817 PDR ADOCK 05000413 P PDR
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L o U. S. Nuclcar Regulatory Commission August 17, 1999 Page 2 xc w/att: L. A. Reyes, Regional, Administrator
'USNRC,- Region II' P. S. Tam, Project Manager USNRC, ONRR D. J.. Roberts Senior Resident Inspector(CNS) l i
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SUMMARY
OF CHANGES l Catawba Nuclear Station l
l Unit 1 and Unit 2 I
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Unit I and Unit 2 Pump and Valve Data Sheets have been refined and reformatted. These changes are reflected as Revision 25 and are listed below. The effective date for the changes as provided by this submittal is May 31,1999 j The general arrangement of the submittal has been changed to align with McGuire and Oconee Nuclear Stations.
GENERAL CHANGES SECTION ARRANGEMENT
=o Unit I and 2 of Pump Program and Unit I and 2 of Valve Program have been consolidated. New Section assignments are as follows:
SECTION CURRENT NEW Pump Inservice Testing Program - Unit 1 Section 3.1 Section 3.1 Pump Inservice Testing Program - Unit 2 Section 4.1 Section 3.1 Valve Inservice Testing Program - Unit 1 Section 3.2 Section 4.1 Valve Inservice Testing Program - Unit 2 Section 4.2 Section 4.1 All other section remain the same as follows:
Catawba Nuclear Station Program Document Section 1.0 Table of Abbreviations Section 2.0 Relief Reauest Section 5.0 Pumps - Generic Relief Request Section 5.1 Pumps - Specific Relief Request Section 5.2 Valses - Generic Relief Request Section 5.3 Valves - Specific Relief Request Section 5.4 Justification For Deferral Section 6.0 Valves - Justification for Deferral Section 6.1 Correspondence Section 7.0 PROGRAM DOCUMENT
=o New section has been added-Thermal Expansion Check Valves, Section 4.5.
=* All Technical Specification Numbers will be changed; therefore numbers have been deleted.
VALVE INSERVICE TESTING TABl.E
=o Several format changes have been made to align with " Guidelines for Inservice Testing at Nuclear Power Plant, NUREG 1482." Included is the addition of valve stroke time, test direction, abbreviation changes, and position indication.
=o Some additional stroke requirements with different test frequencies have been added for some valves. These were added to facilitate the use of other available procedures to stroke valves during other periods such as cold shutdown or refueling.
=o Valves previously listed as Test Requirement 'LJ' which receive NW injection, will be listed as 'LTNW' l
JUSTIFICATION FOR DEFERRAL l =o All Technical Specification Numbers will be changed; therefore numbers have been deleted.
=* All Valve Numbers have been modified to align with Valve Numbers on redesigned data sheets.
=o Additional test requirement information has been added to every Justification For Deferral.
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SUMMARY
OF CHANGES Catawba Nuclear Station Unit 1 and Unit 2 SPECIFIC REVISIONS PUMPS- ADDED TO CATAWBA INSERVICE TESTING PROGRAM INVPU0001C Standby Makeup ;
2NVPU0001C Standby Makeup
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PUMPS - CIIANGES TO PUMP DATA Change in Equipment ID - renumbered lYCPU0001 to OYCPU0001 Change in Equipment ID - renumbered lYCPU0002 to OYCPU0002 i
VALVES-DELETED FROM INSERVICE TESTING PROGRAM System Valves CA - Auxiliary Feedwater System 1(2)CA0171,1(2)CA0172 NW - Containment Penetration I NWOO53, INWOO83, INW0122, I NW0134, INWO146B RN - Nuclear Service Water 1(2)RN0430 VALVES- ADDED TO INSERVICE TESTING PROGRAM System Valves BB - Steam Generator Blowdown Recycle System 1 ( 2 ) B B 0052, 1 ( 2 )B B0053, 1(2 )B B 0054, 1 ( 2 )B B0055 CA - Auxiliary Feedwater System 1(2)CA0255,1(2)CA0256,1(2)CA0257,1(2)CA0291,1(2)CA0292 CF- Feedwater System 1 (2 )CF0028, 1 (2)CF0030, 1 (2 )CF0037, 1 ( 2 )CF0039, 1 (2 )CF0046, 1(2)CF0048,1(2)CF0055,1(2)CF0057 KC- Component Cooling System 1(2)KC0281,1(2)KC0322 ND - Residual lleat Removal System 1(2)ND0116,1(2)ND0117 NI- Safety injection System 1(2)N10052,1(2)N10063,1(2)N10074,1(2)N10086,1(2)N10485 NM -Nuclear Sampling System 1 (2 )N M 0426, 1 (2 )N M 0427, 1 ( 2 )NM0428, 1 (2 )N M 0429 NS - Containment Spray System 1(2)NS0002,1(2)NS0019 NV -Chemical & Volume Control System 1(2)NV0022,1(2)NV0033,1(2)NV0034,1(2)NV0046,1(2)NV0049, 1 ( 2 )N V0057, 1 (2 )NV0060, 1 ( 2 )N V0068, 1 (2 )N V0071, 1 ( 2 )N V0079, 1(2)NV0082,1(2)NV0492,1(2)NV0493,1(2)NV0494,1(2)NV0495, !
1(2)NV0861,1(2)NV0878,1(2)NV0879,1(2)NV0880,1(2)NV0881 RN - Nuclear Service Water System 1(2)RN0030A,1(2)RN0040B SA-Main Steam to Aux Equipment 1(2)SA0001,1(2)SA0004 ;
VI-Instrument Air System 1(2)V10373,1(2)VIO374 8 I WL - Liquid Waste Recycle System 1(2)WLO894,1(2)WLA021,1(2)WLA024 1
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SUMMARY
OF CHANGES Catawba Nuclear Station l Unit 1 and Unit 2 l
l VALVES - GENERIC RELIEF REOUEST - ADDED TO INSERVICE TESTING PROGRAM CN-GRV-01 Safety / Relief Valves Tested Under Ambient Conditions (remove 10 minute hold time)
CN-GRV-02 Safety / Relief Valves Tested At Other Than Ambient Conditions (reduce 10 minute hold to 5 minute hold)
CN-GRV-03 Safety / Relief Valves Tested Under Ambient Conditions (Thermal Equilibrium) l l
l VALVES -SPECIFIC RELIEF REOUEST - ADDED TO INSERVICE TESTING PROGR AM CN-SRV-FD-01 1(2) FD0034,1(2)FD0074 - Diesel Generator Fuel Oil Regulating Valve 1(2)VG0005,1(2)VG0006,1(2)VG0007,1(2)VG0008,1(2)VG0049, CN-SRV-VG-01 1(2)VG0050,1(2)VG0051,1(2)VG0052 - Diesel Generator Starting Air System JUSTIFICATION FOR I'EFERRAL - ADDED TO INSERVICE TESTING PROGRAM The following numbers have been added to the Catawba Inservice Testing Program:
JFD Number Valves CN-CA4)6 1(2)CA0291,1(2)CA0292 CN-CF4)2 1(2)CF0031, 1(2)CF0040, 1(2)CF0(M9, 1(2)CF0058 CN-CF4)3 2CF0166,2CFO167,2CFO168,2CF0169 CN-CF4)4 1(2)CF0028,1(2)CF0037,1(2)CF0046,1(2)CF0055 CN-CF4)5 1(2)CF0030, 1(2)CF0039,1(2)CF0048,1(2)CF0057 CN-FW4)2 1(2)FW0005 CN-NI-24 1(2)N10103 CN-NI-25 1(2)N10125,1(2)N10129 CN-NM4)1 1(2)NM0424,1(2)NM0425 CN-VG-03 1(2)VG0133,1(2)VG0134,1(2)VG0135,1(2)VG0136 CN-WL-01 1(2)WLA022,1(2)WLO321,1(2)WLOS06,1(2)WLO868 Page 3 of 6
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SUMMARY
OF CHANGES Catawba Nuclear Station 1
Unit 1 and Unit 2
- JOSTIFICATION FOR DEFERRAL -SPECIFIC CIIANGES
=> All Technical Specification Numbers will be changes; therefore numbers have been deleted.
=o All Valve Numbers have been modified to align with Valve Numbers on data sheets.
=o Additional information on test requirements have been added to all Justification For Deferrals.
Ji@ Number Valve Number (s) Change CN-CA-01 1(2)CA0037,1(2)CA0N1, Additional comments on Function to clarify position.
1(2)CA0045,1(2)CA0(M9, 1(2)CA0053,1(2)CA0057, 1(2)CA0061,1(2)CA0065 CN-CA-02 2CA0171,2CA0172 Deleted from system.
CN-FW-01 1(2)FW0028,1(2)FW0056 Additional comments on Basis for Deferral to clarify position.
CN-KC-03 1(2)KC0(M7,1(2)KC00279 Valves added to Justification for Deferral.
CN-KC-03 1(2)KC0280 Removed from JFD CN-ND-03 1(2)ND0010,1(2)ND0044 Additional comments on Basis for Deferral to clarify position.
CN-ND-04 1(2)ND0032A,1(2)ND0065B Additional comments on Basis for Deferral to clarify position.
CN-NF-01 1(2)NF0235 Valves added to Justification for Deferral.
CN-N1-(M 1(2)N10060,1(2)N10071 Additional comments on Function to clarify position.
1(2)N10082,(2)N10094 CN-NI-05 1(2)N10471,1(2)N10485 Valves added to Justification for Deferral.
CN-NI-l1 1 (2 )N10124, 1 (2)N10126, 1 (2 )N10128, Additional comments on Function to clarify position.
l(2)N10134,1(2)N10156,1(2)N10157, 1(2)N10159,1(2)N10160 CN-NI-13 1(2)N10165,1(2)N10167, Additional comments on Function to clarify position.
1(2)N10169,1(2)N10171 CN-NI-15 1(2)N10173A,1(2)N10178B Additional comments on Basis for Deferral to clarify position.
CN-N1-16 1(2)N10183B Additional comments on Basis for Deferral to clarify position.
CN-N1-18 1(2)N10332A,1(2)N10333B Additional comments on Function to clarify position.
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CN-NI-19 1(2)N10136B Additional comments on Basis for Deferral to clarify position. '
CN-N1-20 1(2)N10342B Additional comments on Function and Test Alternative to j clarify position. ;
CN-NS-03 1(2)NS0038B,1(2)NSOCM3A Additional comments on Test Alternative to clarify position.
CN-NV-02 1(2)NV0089A,1(2)NV0091B Additional comments on Basis for Deferral to clarify position.
CN-NV-05 1(2)NV0254 Additional comments on Function to clarify position.
CN-NV-06 1(2)NV0270,1(2)NV0290 Additional comments on Function to clarify position.
CN-NV-08 1(2)NV0813 Additional comments on Function to clarify position.
CN-NV-09 1(2)NV0090 Valves added to Justification for Deferral.
CN-NV-12 1(2)NV000! A,1(2)NV0002A Additional comments on Basis for Deferral to clarify position.
CN-NW-02 INWOO53, INWOO83, Reraoved from IST Program INW0122, INW0134 CN-NW-02 All valves listed Removed closing function CN-RN-01 1(2)RN0485 Valves added to Justification for Deferral.
CN VG-02 1(2)VG0025-1(2)VG0028, Corrected procedure number 1(2)VG0069-1(2)VG0072 CN-VI-02 1(2)V10077B Additional comments on Test Alternative to clarify position.
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SUMMARY
OF CHANGES l Catawba Nuclear Station Unit 1 and Unit 2
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VALVES - CHANGES TO INSERVICE TESTING VALVE DATA SilEETS l Valve Number Change l 1(2)CA0023 Test Type from "FSO/C-Q" to *FSO-Q*
1(2)CA0028 Test Type from "FSO/C-Q" to "FSO-Q" ,
1(2)CA0033 Test Type from "FSO/C-Q" to "FSO-Q"
!(2)KC0280 Deleted "FSC-Q" Test i
1(2)FW0005 From " PAS" to "ACT" and Test Type to FSC-Q 1(2)FW0011 From "ACT" to " PAS" ;
I 1(2)FW0013 From "ACT" to " PAS" 1(2)LD0017 Test Type from "FSO/C-Q" to "FSO-Q" 1(2)LD0018 Test Type from "FSO/C-Q" to "FSO-Q"
!(2)LD0047 Test Type from "FSOiC-Q" to "FSO-Q" 1(2)LD0048 Test Type from "FSO/C-Q" to "FSO-Q" 1(2)LD0071 Test Type from "FSO/C-Q" to "FSO-Q" 1(2)LD0072 Test Type from "FSO/CmQ" to "FSO-Q" 1(2)LD0078 Test Type from "FSO/C-Q" to "FSO-Q" 1(2)LD0079 Test Type from "FSO/C-Q" to "FSO-Q"
!(2)NB0262 Test Type from "FSO/C-Q" to "FSC-Q" 1(2)NC0056B Valve Category from "A" to "B" 1(2)NC0057 From % AS" to "ACT" and Test Type to "FSC-Q" 1(2)ND0003 From " PAS" to "ACT" 1(2)ND0031 From " PAS" to "ACT" 1(2)ND0035 From " PAS" to "ACT" 1(2)ND0038 From " PAS" to "ACT" 1(2)ND0064 From " PAS" to "ACT" 1(2)NF0235 Test Type from "FSO/C-Q" to "FSC-Q" 1(2)N10012 Test Type from "FSO/C-Q" to "FSO-Q" 1(2)N10015 Test Type from "FSO/C-Q" to "FSO-Q" 1(2)N10017 Test Type from "FSO/C.Q" to "FSO-Q" 1(2)N10019 Test Type from "FSO/C-Q" to "FSO-Q" 1(2)N10021 Test Type from "FSO/C-Q" to "FSO-Q" j 1(2)N10048 Test Type from "FSO/C-Q" to "FSC-Q" !
2N10101 Removed "LT" Test Requirement 1(2)N10102 From " PAS" to "ACT" 1(2)N10119 From " PAS" to "ACT" 1(2)N10125 From " PAS" to "ACT" 1(2)N10129 From " PAS" to "ACT" i 1(2)NIO151 From " PAS" to "ACT" 1(2)N10161 From " PAS" to "ACT" 1(2)N10351 Test Type from "FSO/C-Q" to "FSO-Q" 1(2)N10352 Test Type from "FSO/C-Q" to "FSO-Q" 1(2)N10353 Test Type from "FSO/C-Q" to "FSO-Q" 1(2)N10354 Test Type from "FSO/C-Q" to "FSO-Q" 1(2)N10471 Valve Category from " A" to "AC" and Test Type to "FSC-Q" 1(2)NM0069 Valve Category from "A" to "AC" l 1(2)NV02% From "ACT" to " PAS" 1(2)NV0218 From "ACT" to " PAS" 1(2)RF0389B Valve Category from "A" to "B" 1(2)RF0392 Test Type from "FSO/C-Q" to "FSC-Q" I
1(2)RF0447B Valve Category from"A" to "B" 1(2)RF0448 Test Type from "FSO/C-Q" to "FSC-Q" 1(2)RN0405 Test Type from "FSO/C-Q" to "FSC-Q" 1(2)RN0438 Test Type from "FSO/C-Q" to "FSC-Q" Page 5 of 6
SUMMARY
OF CIIANGES Catawba Nuclear Station Unit 1 and Unit 2
< Yhive Number Change 1(2)VB0085 Test Type from "FSO/C-Q" to "FSC-Q" 1(2)VG0005 Type Frequency from "Q" to "M" 1(2)VG0006 Type Frequency from "Q" to "M" ;
1(2)VG0007 Type Frequency from "Q" to "M" l 1(2)VG0008 Type Frequency from "Q" to "M" I 1(2)VG0049 Type Frequency from "Q" to "M" 1(2)VG0050 Type Frequency from "Q" to "M" 1(2)VG0051 Type Frequency from "Q" to "M" i 1(2)VG0052 Type Frequency from "Q" to "M" 1(2)V10079 Test Type from "FSO/C-Q" to "FSC-Q" 1(2)V10367 Test Type from "FSO/C-Q" to "FSC-Q" l 1(2)V10368 Test Type from "FSO/C-Q" to "FSC-Q" l 2VS0054 Change Test Requirement "LT" to "LJ" 1(2)VS0056 Test Type from "FSO/C-Q" to "FSC-Q" 1(2)VY0016 Test Type from "FSO/C-Q" to "FSC-Q" 1(2)WLO321 Test Type from "FSO/C-Q" to "FSC-Q" 1(2)WLO805A Valve Category from "A" to "B" 1(2)WL0806 Test Type from "FSO/C-Q" to "FSC-Q" 1(2)WLO807B Valve Category from "A" to "B" 1(2)WL0825A Valve Category from "A" to "B" 1(2)WLOS27B Valve Category from "A" to "B" 1(2)WLO867A Valve Category from "A" to "B" 1(2)WLOS68 Test Type from "FSO/C-Q" to "FSC-Q" 1(2)WLOS69B Valve Category from "A" to "B" 1(2)WLA0022 Test Type from "FSO/C-Q" to "FSC-Q" 1(2)YM0121 Test Type from "FSO/C-Q" to "FSC-Q" 1SV0009 Act. Type from "AO" to "S A" ISV0010 Act. Type from "MO" to "SA" ISV0011 Act. Type from "AO" to "S A" 1SV0012 Act. Type from "AO" to "SA" 2SV0009 Act. Type from "AO" to "S A" 2SV0010 Act. Type from "AO" to "SA" 2SV00ll Act. Type from "AO" to "S A" 2SV0012 Act. Type from "AO" to "S A" lYC0065 Test Type from "FSC-Q" to "FSO-Q" IYC0108 Test Type from "FSC-Q" to "FSO-Q" i
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