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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] Category:UTILITY TO NRC
MONTHYEARML20059L5491990-09-14014 September 1990 Forwards Proprietary Response to Question Re Scope of Review of Topical Rept, Safety Analysis Physics Parameter & Multidimensional Reactor Transients Methodology, Per & 900723 Meeting.Response Withheld ML20059L5521990-09-14014 September 1990 Forwards Response to 18 Questions Re Topical Rept DPC-NE-2004,per NRC 900802 Request for Addl Info.Encl Withheld (Ref 10CFR2.790) ML20059K2021990-09-12012 September 1990 Submits Supplemental Response to Generic Ltr 89-14, Svc Water Sys Problems Affecting Safety-Related Equipment. Intake Structure Insp Program Developed.Procedures for Insp Implemented & Intake Structures Sampled & Analyzed ML20064A8041990-09-0505 September 1990 Notifies NRC of Mod to 890301 Response to Violations Noted in Insp Repts 50-413/86-18-01 & 50-414/86-18-01 Re Valves. All Valve Locking Mechanisms Would Be Installed by End of Unit 2 Refueling Outage (Approx Aug 1990) ML20064A5741990-09-0404 September 1990 Discusses Re Info to Support Util Position Relative to Resolving Issue of Main Steam Line Breaks Inside Ice Condenser Containments & Requests That Info Be Withheld (Ref 10CFR2.790) ML20059G3011990-09-0404 September 1990 Forwards Response to NRC 900327 Request for Addl Info Re BAW-10174, Mark-BW Reload LOCA Analysis for Catawba & Mcguire ML20059G8321990-08-30030 August 1990 Withdraws 880726 Proposed Tech Spec Change,Clarifying Tech Spec 3/4.7.6 Re Emergency Power Requirements for Control Room Ventilation Sys ML20059D2011990-08-27027 August 1990 Forwards Piedmont Municipal Power Agency , Authorizing Use of Annual Rept for NRC Docket Requirements ML20059D2441990-08-24024 August 1990 Forwards Special Rept PIR-1-C90-0261 on 900725 Re Cathodic Protection Sys Failure to Pass Acceptance Criteria of 60-day Surveillance.Std Work Request Generated to Check Voltage Potential at Test Station TS-36 on Weekly Basis ML20056B4981990-08-22022 August 1990 Responds to NRC Request for Addl Info Re General Relief Request for Pump Vibration Submitted 900315.Relief Request Changed to Insure Data Taken Over Range That Encompasses All Main Potential Noise Contributors ML20056B5011990-08-22022 August 1990 Responds to Violation Noted in Insp Repts 50-413/90-17 & 50-414/90-17.Corrective Actions:Review Will Be Conducted to Determine Category of Infrequently Run Procedures Needing Addl Verification Controls ML16259A2391990-08-22022 August 1990 Forwards Public Version of Rev 27 to Company Crisis Mgt Implementing Procedure CMIP-2, News Group Plan. W/ Dh Grimsley 900906 Release Memo ML20056B4971990-08-20020 August 1990 Clarifies Info Submitted in 871207 & s Re Steam Generator Tube Rupture Analysis Demonstration Runs. Demonstration Runs Met plant-specific Requirements in Section D to NRC SER on WCAP-10698 ML20059C1201990-08-20020 August 1990 Forwards Rept Summarizing Util Findings Re Three False Negative Blind Performance Urine Drug Screens Which Occurred During Jan & Feb 1990.Recommends That NRC Consider Generic Communication to Clearly State Reporting Requirement ML20059B6581990-08-17017 August 1990 Responds to Violation Noted in Insp Repts 50-413/90-15 & 50-414/90-15.Corrective Actions:Present Methods of Testing Operability of CO2 Fire Protection Sys Will Be Evaluated by 910201 to Determine If Addl Testing Necessary ML20059C1591990-08-17017 August 1990 Suppls by Providing Addl Info to Support Util Position Re Anl Confirmatory Analysis of Main Steamline Breaks in Ice Condenser Plants.Encl Withheld ML20063Q0951990-08-15015 August 1990 Forwards Monthly Operating Rept for Jul 1990 for Catawba Nuclear Station Units 1 & 2 & Revised Rept for June 1990 ML20059C1231990-08-15015 August 1990 Advises That Util Submitting Special Rept Re Valid Failure of Diesel Generator 2B Would Be Delayed Until 880229 Had Incorrect Ltr Date.Date of Ltr Should Have Been 880204 Instead of 880104.Corrected Ltr Encl ML20063Q2671990-08-14014 August 1990 Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 36 to CMIP-1,Rev 32 to CMIP-4,Rev 36 to CMIP-5,Rev 41 to CMIP-6,Rev 40 to CMIP-7,Rev 27 to CMIP-8 & Rev 35 to CMIP-9.W/DH Grimsley 900821 Release Memo ML20059C2211990-08-13013 August 1990 Forwards Revised Chapter 16, Selected Licensee Commitments Manual, to Plant Updated Fsar,Per 10CFR50.4 & 50.71.Manual Contains Commitments Which Require Control But Not Appropriate in Tech Specs ML20063Q0261990-08-10010 August 1990 Forwards Rev 0 to Catawba Unit 2 Cycle 4 Core Operating Limits Rept, Per Tech Spec 6.9.1.9 ML20063Q0671990-08-10010 August 1990 Submits Revised Response to Violations Noted in Insp Rept 50-413/90-09.Procedure to Verify Test Inputs Modified to Verify Dummy Input Signal to Channel RTD Circuit ML20058N0181990-08-0808 August 1990 Forwards Response to Request for Addl Info Re BAW-10174, Mark-BW Reload LOCA Analysis for Catawba & Mcguire ML20081E1601990-08-0101 August 1990 Advises of Completion of 900330 Commitment Re Standing Work Request for Insp of Air Flow Monitors & Dampers,Per Violations Noted in Insp Rept 50-413/90-03 & 50-414/90-03 ML20058P3261990-08-0101 August 1990 Forwards Public Version of Rev 26 to Station Directive 3.8.4, Onsite Emergency Organization ML20081E0951990-07-27027 July 1990 Forwards Decommissioning Financial Assurance Certification Rept for Duke Power Co,co-owner of Catawba Nuclear Station Units 1 & 2 ML20055H9741990-07-26026 July 1990 Forwards end-of-cycle 3 Steam Generator Insp Rept.Nineteen Tubes Removed from Svc by Plugging W/Rolled Mechanical Plug ML20055H5231990-07-24024 July 1990 Discusses co-licensee Relationship & Obligations Re Decommissioning Financial Assurance for Facilities ML20055H4571990-07-19019 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-413/90-11 & 50-414/90-11.Corrective actions:I-beams/ Hoists Rolled to Ends of Ice Condenser & Securely Located on Rails to Prevent Any Movement ML20055H1741990-07-18018 July 1990 Withdraws 880527 & 0725 Amends Clarifying Requirements for Containment Pressure Control Sys ML20055J3441990-07-17017 July 1990 Advises That Commitment Re Procedure IP/O/A/3190/01,per Violation in Insp Repts 50-413/90-06 & 50-414/90-06, Completed on 900619 ML20055H4131990-07-16016 July 1990 Forwards Public Version of Epips,Including RP/0/A/5000/07 & HP/0/B/1009/04 ML20055F8991990-07-13013 July 1990 Forwards Monthly Repts for June 1990 for Catawba Nuclear Station Units 1 & 2 & Operating Status Rept for May 1990 ML20055G2311990-07-13013 July 1990 Withdraws 880311 Proposed Amend to Tech Spec Table 3.3-3, Item 8.f Re Number of Instrumentation Channels Associated W/ Main Feedwater Pumps.Util Determined That Change Unnecessary ML20055F8461990-07-12012 July 1990 Requests 14-day Extension Until 900802 to Submit LER 414/90-010 to Investigate Power Supply Realignment ML20058P1231990-07-0707 July 1990 Advises That Commitment to Revise Maint Mgt Procedure 1.12 to Include Functional Verification Requirements & to Develop Retest Manual to Address Retest Requirements for Any Maint Performed on Components Completed on 900614 ML20055F4131990-07-0505 July 1990 Forwards Inservice Insp Rept Unit 1 Catawba 1990 Refueling Outage 4, Per 10CFR50.55(a)(q) & Tech Spec 4.0.5.Insp Performed Per Section XI of ASME Boiler & Pressure Vessel Code & Applicable Addenda ML20055D4291990-06-29029 June 1990 Supplemental Response to Violations Noted in Insp Repts 50-413/89-13 & 50-414/89-13,per .Personnel Responsible for Maintaining Crisis Mgt Ctr Drawing Trained. Util Will Continue to Evaluate Changes Made to Program ML20055E2191990-06-29029 June 1990 Submits Revised Commitment Dates Re Implementation of Dept Guidance on post-maint Testing,Per Commitment Made in 891002 Response to Violations in Insp Repts 50-413/89-19 & 50-414/89-19.Completion Date Changed to 900701 ML20044B0621990-06-26026 June 1990 Forwards Public Version of Revised EPIP HP/0/B/1009/05, Personnel/Vehicle Monitoring for Emergency Conditions. W/Dh Grimsley 900716 Release Memo ML20043H6921990-06-18018 June 1990 Advises of Revised Completion Date for VA Ductwork Cleaning to 901231,per Insp Repts 50-413/90-03 & 50-414/90-03. Vendor Personnel Assigned to Task Unavailable to Complete Cleaning Until Late 1990 Due to Outage Support Needs ML20043G1691990-06-15015 June 1990 Forwards Monthly Operating Repts for May 1990 for Catawba Nuclear Station,Units 1 & 2 & Corrected Monthly Operating Repts for Apr 1990 Re Personnel Exposure ML20055C8041990-06-15015 June 1990 Responds to NRC Re Violations Noted in Insp Repts 50-413/90-10 & 50-414/90-10.Corrective Actions:Instrument Root Valves Unisolated & Analog Channel Operational Tests for Low Temp Overpressure Protection Completed ML20043G4331990-06-13013 June 1990 Withdraws 900423 Proposed Amend to Tech Spec 4.6.1.8 Re Lab Test of Carbon Samples from Annulus Ventilation Sys ML20043G3771990-06-13013 June 1990 Withdraws 900423 Proposed Amend to Tech Spec 4.7.7 Which Required That Lab Test of Carbon Samples from Auxiliary Bldg Filtered Exhaust Sys Be Tested for Methyl Iodide Penetration of 0.71% ML20043G2511990-06-12012 June 1990 Withdraws 900419 Suppl to 871221 Application for Amends to Licenses NPF-35 & NPF-32 Re Tech Specs 4.7.6 Re Control Room Area Ventilation Surveillance Requirements ML20043G1741990-06-0707 June 1990 Responds to Request for Addl Info Re BAW-10174, Mark-BW Reload LOCA Analysis for Catawba & Mcguire. Correct RCS Operating Pressure Would Be 2,250 Psia as Identified in Table 3-1 ML20043G3451990-06-0707 June 1990 Forwards Proprietary Response to Request for Addl Info Re Topical Rept BAW-10174, Mark-BW Reload Safety Analysis for Catawba & Mcguire. Response Withheld ML20043G0721990-06-0707 June 1990 Responds to NRC 900510 Ltr Re Violations Noted in Insp Repts 50-413/90-09 & 50-414/90-09.Corrective Actions:Vc/Yc Train a Returned to Svc W/Supply Power from 2ETA.Terminal Box 1TB0X0346 Inspected & Insured Operable ML20043F6111990-06-0606 June 1990 Advises That Response to Request for Addl Info Re Operator Response Times During Simulated Steam Generator Tube Rupture at Facility,Will Be Delayed Until 900630 1990-09-05
[Table view] |
Text
-. .
.- a DUKE Powen GOMPANY P.O. DOX 33180 CHARLOTTE. N.C. 28242 HALH. TUCKER ren.erssown vacu renomer (704) 373-4531 December 31, 1984 Mr. D. G. Eisenhut Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Re: Catawba Nuclear Station Docket Nos. 50-413, 50-414
Dear Mr. Eisenhut:
Our response of November.4, 1983 to Generic Letter 83-28 described our efforts regarding Item 3.1.2, Review of Vendor Engineering Recommendations for Reactor Trip System Components. We have completed our review of applicable Data Letters and Bulletins, the results of which can be found in Attachment 1. This review included Westinghouse data letters and technical bulletins for all other safety-related components as well.
In response to Item 4.2 please find Attachment 2, a descripuion of the Preventative Maintenance Program for Reactor Trip Breakers which is currently in use at Catawba.
This is accomplished through procedure MP/0/A/2001/05, a copy of which is included.
As discussed in our original response of November 4, 1983, the results of the
. Life Cycle Testing program which was conducted by Westinghouse for the Westinghouse Owner's Group are to be incorporated into an updated Instruction Manual from Westinghouse. A replacement program for reactor trip system components will be ,
incorporated into an upgraded Duke maintenance program when the new manual is issued.
In our status letter of November 2, 1984, the scheduled implementation date for the component replacement program was incorrectly stated as December 31, 1984.
Based upon timely receipt of the new Westinghouse manual implementation of the
- component replacement program at Catawba is expected by the end of the first scheduled refuelirig outage.
Very truly yours, d /$p _ - - .
Hal B. Tucker j LTP/mjf 0 tI1 Attachments (
8501070328 841231.
' PDR ADOCK 05000413:
PDR:
p L _ _.
- i- ..'. .
Mr. D. G. Eisenhut, Director '
, December 31,.1984 Page two.
cc: Mr..J. P. 0'Reilly, Regional Administrator U. S.' Nuclear Regulatory Commission
' Region'II. .
" 1101 Marietta Street, ~MJ, Suite 2900
-Atlanta,. Georgia 30302-
, : Mr. R. A.- Birkel Division of Project Management
< Office of Nuclear Reactor Regulation U.-S.-Nuclear Regulatory Commission
' Washington, D.-C. 20555 Robert' Guild, Esquire
. Attorney-at-Law P. 0.-Box 12097 Charleston, South Carolina 29412 Mr. Jesse.L. Riley .
Carolina Environmental Study Group 854 Henley Place Charlotte,' North Carolina 3
-Dr. K. N. Jabbour-NRC Project Manager Office of Nuclear Reactor Regulation l- U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Ms.. Helen Nicolaras, Project Manager Office of Nuclear Reactor Regulation
- U. S.; Nuclear Regulatory Commission Washington, D. C. 20555 -
Mr.'J..C. Bryant LNRC Resident. Inspector-Oconee F.tclear Station LMr.'W. T. Orders NRC Resident Inspector
- McGuire Nuclear Station NRC Resident. Inspector
. Catawba Nuclear Station PalmettoLAlliance-2135 Devine Street
, Columbia..So'uth Carolina 29205-
~
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ATTACHMENT 1 DATA LETTERS 63-2 Nuclear Maintenance I & E concurs with Design Engineering that appropriate noise reduction techniques were utilized in the design and construction of Catawba Nuclear Station. Catawba I & E has agreed that appropriate noise reduction techniques will be considered
-in the implementation of future NSM packages. Furthermore, Catawba Projects has agreed to make their personnel aware of these techniques.
63-5 The only mineral insulated cable we are aware of at Catawba is the cable used in the nuclear instrumentation and incore thermocouple applications. In both cases, vendor supplied, prefabricated cables were used (the cables and plugs were already assembled and ready to use). Therefore, this item does not affect Catawba. However, as a precaution the station was notified that any mineral insulated cable which is formed by site personnel for any future application should be heat dried just before sealing.
64-4 The use of any item containing lead within the primary system is controlled by a Materials Guide.and by Station Directives.
68-14 This Data Letter was originally written by Westinghouse with reference to their old 7100. series equipment, and is therefore not applicable to Catawba. Furthennore, the Precautions, Limitations & Setpoints manual is used to determine the proper setpoints.
68-25 The Vital Bus is never used to supply non-vital loads at any time.
68-31 The content of this Data Letter has been superseded.
68-36 This Data Letter is not applicable to Catawba Nuclear Station.
70-18 All essential equipment utilizing triaxial cable has been success-fully preoperationally tested. Furthermore, any faulty cable would already have been discovered during installation or testing.
71-20 There has been no problem with drifting output signals on Barton transmitters. If there were any defective transmitters at Catawba, they would have been noticed by now. However, if any problems are noted, either the site Westinghouse representatives or Barton-representatives will be notified.
73-8 Breakers at Catawba Nuclear Station were originally sized based on manufacturer's specifications on the electrical loads, and also on Design Engineering calculations of the maximum motor starting current '
- through each breaker. Any incorrectly sized breakers would be noticed during periodic breaker testing and preventative maintenance.
5
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ATTACHMENT 1 1
- 74-4 'No action by Duke Power Company. is required - this Data Letter was
, transmitted for our information.
77-2 Catawba Nuclear Station already uses the Keithley 602 electrometer.
77-3 This Data Letter is not applicable to Catawba Nuclear Station.
78-4 The recommended changes will be made to the appropriate instrument calibration procedures by Catawba I & E.
79 Station procedures specify the use of permanently installed voltmeters to ensure proper P-4 permissive contact operation following all reactor trips. .These voltmeters were installed as a modification in
. response to a Westinghouse letter of 11-7-79 to the NRC.
80-3 .The proper connectors have already been ordered as spares, and the necessary instructions for their use are already in the appropriate instrument procedure..
80-8' It is a common practice of Catawba I & E to " exercise" the calibration potentiometers of a transmitter if the output of that transmitter is not steady.
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ATTACHMENT 1 TECHNICAL BULLETINS 73-24 Rev. 1 The potential for RF I & C interference as a result of the use of radio equipment within the station has already been addressed in response to IE Information Notice 83-83.
Catawba Nuclear Station has established administrative controls on areas where transmitter use will not be allowed.
74-12 No action is necessary for Catawba Nuclear Station Unit 1, as construction has been completed for this unit. Catawba Constrection has committed to notify / train the electrical crews of this situation by December 31, 1984, in order to be alert for this potential problem on Unit 2. This training will be documented on Construction Training Form V-lC.
75-2 This Technical Bulletin is not applicable to Catawba Nuclear Stu tion.
77-10 The actions recommended by this Technical Bulletin have been completed.
80-4 Catawba Nuclear Station was alerted to the possibility of the subject voltage oscillations occurring, and were instructed to notify both Westinghouse and Nuclear Maintenance I & E if any such oscillations are observed. None have been seen to date.
80-5 Catawba Nuclear Station plans to always use a reference power level of 100%, with Incore Axial Offset data taken at 75%.
However, a note will be added to the appropriate instrument i procedure by I & E to. provide proper scaling for other refer-ence power levels.
80-6 This bulletin is not applicable, since Catawba Nuclear Station does not utilize 10-50 mA transmitters.
I 80-8 This Technical Bulletin is not applicable to Catawba Nuclear Station.
L 81-11 - Action on this Technical Bulletin has been completed for Catawba Nuclear Station.
81-13 Catawba Nuclear Station was not affected by this Technical Bulletin.
b
Attachment 2 I
l Catawba Nuclear Station Westinghouse DS-416 Reactor Trip Breakers i Summary of Preventative Maintenance Program The subject breakers are cleaned, inspected, and tested every six months under procedure MP/0/A/2001/05. A description of the preven-tative maintenance follows below:
The breakers are given a visual inspection as they are removed from service. If any cracked welds, broken parts, and/or loose or missing bolts are discovered, repairs are made immediately. The breakers are then cleaned by means of vacuum, compressed air, or an oil free solvent.
The cubicle is cleaned, and lubricated if necessary. Next, the arc chute shields, barriers, covers, and arc chutes are removed (wet arc chutes or insulators are dried with a suitable heat source).
A Force Test on the Trip Bar is performed, fo!1 owed by a Force Test on the UV Trip Device (the Trip Load must be less than 2 lbs., and the acceptance criteria for the latter test is 3.0 lbs. minimum). Pre and Post Travel tolerances for the Trip Tap on the UV Trip Device are checked. (No adjustments to the UV Trip Attachment are allowed to satisfy clearance requirements within the device or between the device and the reactor trip breaker shaft lever pin, unless a Westinghouse service representative is present. If a UV device is in need of repair and no Westinghouse representative is present, a new UV device is installed). Proper cleanliness and lubrication of the roller bearing is verified.
An inspection of.the contacts is now performed. They are cleaned, and contact wipe, contact resistance, pressure, and alignment are checked (see Attachment 3 for a drawing showing the alignment tolerances checked).
The mechanism linkage is checked for proper operation, including an.
inspection of every pin, keeper, or spring used in the assembly. Any necessary repairs are made. All other measurements and adjustments
- required by the instruction manual (CNM-1399.40-00ll) are made,'and then the equipment is lubricated and cleaned.
Finally, the breaker is tested mechanically and electrically for proper operation. The Force Tests on the Trip Bar and UV Trip Device are performed again, and the Pre and Post Travel tolerances for the Trip Tap on the UV Trip Device are again checked. The roller bearing is re-examined, and then the breaker is cycled ten times (using the UV trip device).
Finally, all parts which were earlier removed (chutes, shields, etc.)
are reinstalled.
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Form 34731 (1041)
(Formerly SPD 10021) 1 l
DUKE POWER COMPANY (1) ID No: HP/0/A/2001/05 PROCEDURE PREPARATION PROCESS RECORD Change (s) 0 to 0 Incorporated (2) STATION: Catawba Nuclear (3) PROCEDURE TITLE:_ Westinghouse DS-416 Air Circuit Breaker Insoection and Staintenance (4) PREPARED BY: Jeff Ashe DATE: 11/17/83 J>
(5) REVIEWED BY: [. 8e m / DATE: 2!/,5 /99 Cross-Disciplinary Review By: SI N/R: S/20 W!f
(
/e (6) TEMPORARY APPROVAL (IF NECESSARY):
By:
(SRO) Date:
By: Date:
( (7) APPROVED BY: me MC Date: .3-2-N (8) MISCELLANEOUS:
- Reviewed / Approved By: Date: ((-/2 " b F
Reviewed / Approved By: Date:
REYlEWED BY QUAmY ASSURANCE DEARTMENT This' copy ~&as'6een's rpared OPERATIONS DMSION the cetrol co -
corret Rd 18 Yerified Y Y$ 2-/.SN O Eat E REPRESENTATIVE DATE N
. ar: , -
Procedure TCP/CN0/A/0006/00/0/SM (MP/0/A/2001/05)
QA Department)A Review A( N Date Section p f Approval _4 V Date /2-/2- O 90 DUKE POWER COMPANY TRANSMISSION DEPARTMENT SUBSTATION DIVISION MAINTENANCE SECTION ,
CHARLOTTE DISTRICT / GROUP CATAWBA LOCATION / STATION WESTINGHOUSE DS-416 AIR CIRCUIT BREAKER IN$PECTION AND MAINTENANCE NOTE: Sections in this procedure that are preceded by an asterisk shall be initialed on Enclosure 13.1 of this procedure. Double asterisks indicate QA inspection steps. Sign off in step 11.16.
1.0 Purpose 1.1 This procedure establishes the requirenents to control the inspection and maintenance of Westinghouse DS-416 breakers.
2.0 References 2.1 Current copy of Instruction Manual for DS-416 Breakers. CNM 1399.40-0011.
2.2 Westinghouse Drawing No. 693C350.
2.3 Westinghouse Drawing No. 588C785.
3.0 Personnel Requirements 3.1 The number of manhours necessary to complete the inspection and testing depends on the extent of repairs to be made. Record actual manhours on the work request.
3.2 Personnel performing maintenance on Westinghouse DS-416 breakers shall have qualifications satisfying Catawba Nuclear Station Directive 2.7 and the Transmission Administrative Manual Section 2.3.
4.0 Safety Considerations 4.1 Equipment Clearance and Isolation
-4.1.1 Breaker maintenance will require that the breaker be racked out to the disconnect position and placed on the floor. Red tags should be issued if needed according to Catawba Nuclear Station Directive 3.1.1.
545001H
- . . _ _ _ . .- . . _ . . =. ._. _ _ _
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4.2 Health Physics Considerations 4
4.2.1 If the work request indicates, obtain a Radiation Work Permit or a Standing Radiation Work Pemit from Health Physics.
) 4.3 Special Safety Considerations 4.3.1 Assure good ventilation or use air masks when using "Penolene",
" Spot Check", or similar chlorinated hydrocarbon cleaners.
4.3.2 Use red tape to identify any exposed high voltage creas and warn personnel of any possible shock hazards.
- 5.0 .
Station (or Unit) Status l'
- 5.1 Routine maintenance on breakers should coincide with PM requirements and Technical Specification requirements. Availability should be determined by the shift supervisor or his superior, in order to insure safe unit operation.
6.0 Prerequisites
- 6.1 Verify that this procedure is the same as the control copy at the p station.
- 6.2 Notify Quality Assurance personnel before beginning work if the
+
Work Request so indicates.
i *6.3 Before or during the job, the job supervisor, planner, or engineer shall review, the job. initial and "N/A" any procedure steps that are not applicable to li *6.4 If necessary, obtain current manufacturer's drawings and/or instruction books.
-**6.5 While performing this procedure if any leads are lifted, jumpers added, or switches opened or closed, double verification of removal and double verification of replacement must be documented on Enclosure 13.2.
7.0 Repair Parts 7.1 Work on safety related breakers will require - Quality Assurance approved parts.
7.2-Parts utilized during repairs will be listed 'on the Work Request.
The Work Request must be presented at the parts room to obtain parts.
- l. 8.0 Special Tools
- 8.1 Verify that calibration dates on tools and measurement equipment are cu* rent.
Record serial number and calibration date due. on Enclosure 13.2.
- 545001H
9.0 Acceptance Requirements Note: This section is applicable only when a complete PM of the breaker is perfonned and need not be initialed when making minor repairs or adjustments that may arise between scheduled PM periods.
- 9.1 The successful completion of the applicable parts of Section 11.0 of this procedure will detemine the acceptability of the A. C. B.
10.0 Interference Items None 11.0 Procedure Note: The following steps are not necessarily required to be performed in chronological order. Some steps may be performed at any time. This procedure is to be used as a guide by experienced breaker retairmen only.
- 11.1 Verify that the Work Request has been approved, and the " Clearance to Begin Work" section has been properly completed. Be sure the breaker is de-energized and/or red tagged. Maintain all enclosum: + bat are applicable to the maintenance activity being performed.
- 11.2 Visually check equipment as removed from service. Inspect the equipment for broken parts, cracked welds, and/or loose or missing bolts.
Repair or replace any damaged parts and record action taken.
- 11.3 Remove dust and dirt by vacuum, air, or oil free solvent.
- 11.4 Clean and inspect cubicle for loose hardware or broken parts and lubricate where necessary.
- 11.5 Remove are chute shields, barriers, covers, and arc chutes. " Wet" arc chutes or insulators may be dried with a heat gun, oven, or other heat source.
- 11.6 Perform the following tests and record the data obtained on Enclosure 13.3. Include the total number of times the breaker was tripped.
Before preventive maintenance testing on UV trip device "AS FOUND" Westinghouse Drawing No. 693C350 and No. 58SC785 should be consulted if needed.
11.6.1 Perform a Force Test on the Trip Bar.
11.6.2 Perform a Force Test on the UV trip device.
11.6.3 Check the tolerances regarding Pre and Post Travel of the Trip Tap on the UV trip device.
545001H
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- 11.6.4 Check the condition of the roller bearing with regard to the proper cleanliness and lubricant.
r 11.6.5 Should a UV device be found faulty and adjustments cannot be made, field installation of a new UV device should .be made as per Westinghouse Drawing No. 588C735. No adjustments to the undervoltage trip attachment are to be made in the field to satisfy either intracisarance requirements (within the device proper) or interclearance requirements (between the device and the ,
RTB trip shaft lever pin) without an appropriate Westinghou e service representative present.
- 11.7 Inspect the' ' contacts; clean, check contact dipe, contaci resistance, pressure ard alignment. This includes checking measurements as y per instruction book. ' Repair or replace as needed. ,
F .
$ **11.8 Inspect mechanism linkage for binding, looseness, worn or defective i parts. Check every pin, keeper, and spring in the mechanisn. Repair or replace as needed. c 3
- 11.9 Make and/or check any mechanism measurements and adjustments needed n
.per instruction or technical bulletins and record on Enclosure 13.1.
- 11.10 Lubricate and perfonn finai cleantag of the equipmept.
s
- 11.11 Check breaker operation mechapi t ally and electrically.
- 11.12 Ferform the following tests and record the data obtained on Enclosure =13.3. ;, . ,f
'[
After preventive maintenance testing of UV device "AS LEFT" s e
m Westinghouse Drawing rio F needed. 69.'C350 and No. 588C785 should be consulted if J
- **1.1.12J , Perform a Force Tes : in the Trip Bar.
t b **11.12.2 Perform a Force Test on the UV Trip Device, r f
[
- '11.12.3 Check the tolerances regarding Pre and Post Travel of' the Trip Tab
'on the UV Trip Device. ,
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~
9 .
- 11.12.4 Check the condition of the miler bearing with regsrd to the proper .
/
t- cleanliness and lubricant. >
s
- 1
- 11.13 a device. Report On the test bench, Sycle the breaker ten times udng the UV trip Ew any failuresip appropriate personnth
[ **11.14
/
Install necessary parts (chutes, chields, and /ront cover).
Complete all documentation on the Work Request and the Enc'icsures.
4
- 11.16 Q.C. inspector veriff es that $lh inspectioris with double asterisks
/g 5 qave been performed.
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T 12.0 Restoration
- 12.1 Contact the shift supervisor to clear the red tags if any were issued and return the breaker to the station for operation.
- 12.2 Notify the I&E group for additional testing requirements.
i
- 12.3 Forward the completed copy of the Work Request and applicable enclosures to the Planning Office or the Station Support Engineer.
13.0 Enclosures 13.1 Procedure Checklist 13.2 Tool, Instrument, and Torque Value List 13.3
! Force Tests and Tolerance Checks for UV Device S
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ENCLOSURE 13.1 PROCEDURE CHECKLIST TCP/CN0/A/0006/00/0/SM Foreman W.R. #
Date Breaker Nameplate: Type Mfr Volts Amps .
Serial #
5.1 Status 11.8 Mechanism 6.1 Verification 11.9
__ Adjustments 6.2 QA 11.10 Lubrication
- 6. 3 - Review 11.11 Operation 6.4 I.B. 11.12 As left 6.5 Leads 11.13 Cycle 9.1 Acceptance 11.14 Arc Chutes 11.1 Clearance 11.15 Document tion 11.2 Visual 11.16 QC 11.3 Dust 12.1 S.S.
11.4 Cubicle 12.2 18E 11.5 Arc Chutes 12.3 Forward .
11.6 As Found 11.7 Contacts Contact resistance left Middle Right Comments or Discrepancies:
i 545001E
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ENCLOSURE 13.2 TOOL, IE3TRUMENT, AND TOROUE VALUE LIST TCP/CN0/A/0006/00/0/SM WORK REQUEST INSTRUMENT / TOOL SERIAL NUMBER CALIBRATION DUE DATE I
ITEM TORQUED TORQUE VALUE QC INSPECTOR 4
f List Leads Lifted / Jumpers Added or switches opened Terminal /Etc Date Removed Verified By Date Returned Verified By
/ /
/ '/
/ /
/ / ;
r 3
i 545001E
ENCLOSURE 13.3 FORCE TESTS AND TOLERANCE CHECKS OF THE UV DEVICE '
FOR WESTINGHOUSE DS-416 BREAKERS TCP/CN0/A/0006/00/0/SM Breaker Group
_ Name BEFORE PREVENTIVE MAINTENANCE TESTING ON UV TRIP DEVICE 11.6.1 Force Test on Trip Bar 1bs.
(Trip load less than 2 lbs. Indicates satisfactory operation) 4 11.6.2 Force Test on UV Trip Device 1bs.
(3.0 lbs. minimum) 11.6.3 Tolerance of o e-Travel was inches.
(.03inchF.dmum)
Tolerance et Post Travel satisfactory (Yes or No) 11.6.4 Condition of roller bearing satisfactory (Yes or No)
AFTER PREVENTIVE MAINTENANCE TESTING ON UV TRIP DEVICE (A! L 11.12.1 Force Test on Trip Bar
. lbs.
(Trip load less than 2 lbs. indicates satisfactory operation) 11.12.2 Force Test on UV Device 1bs.
(3.0 lbs. minimum) 11.12.3 - Tolerance of Pre-Travel inches.
Tolerance of Post Travel acceptable (Yes or No) 11.12.4 Condition of roller bearing satisfactory (Yes or No)
TOTAL NUMBER OF TIMES BREAKER WAS TRIPPED .
5 545001E
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Athkment- 3
- 70 12.1.1 When to Inspect tion shows, for instance, heavy accimtulations of dirt or Industry standards for this type of equipment recommend other foreign matter that might cause mechanical, insula. o i a general inspection and lubrication after the number of tion or other electrical damage, the inspection and maintenance interval should be decreased, I operations listed in Section 123.1 of this instruction y
f book. 'Ihis should also be conducted at the endWhen of thea breaker opens a heavy fault, at or near its of fust six months of service if the number of operations has 7
not been reached. rating, give it a visual inspection withdrawn from the -
C mPartment and with insulating barriers and are chutes removed.
After the first inspection, inspect at least once a year, if these recommended inspections show no inaintenance1 .l. t to Inspect requirements, the period may be extended to a more First economical point. Conversely,if the recommended inspec. withdraw the breaker from the compartment.
Remove barriers. Remove are chutes. If there is a depo C ,, r .02o to .060 A C ,,_,
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-0.421 D8 '
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- 3 Fig. 85 Contacts and their AJjustment, DS416l420 Breaker
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