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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:OUTGOING CORRESPONDENCE
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 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 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 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 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 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 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 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 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 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 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 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 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 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 ML20209E2701999-07-0101 July 1999 Forwards Insp Repts 50-413/99-03 & 50-414/99-03 on 990425- 0605.Six Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20209E3931999-06-28028 June 1999 Informs of 990618 Meeting Conducted at Facility to Present Results of Most Recent Periodic Plant Performance Review for Plant.List of Attendees Encl ML20196G8861999-06-24024 June 1999 Discusses GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structrual Integrity 950816 & 960729 Responses.Rvid,Version 2 Released as Result of Review.Rvid Should Be Reviewed & Comments Should Be Received by 990901 If Not Acceptable for Plant ML20196G6541999-06-17017 June 1999 Confirms 990614 Telephone Conversation Re Rescheduling of Two Predecisional Enforcement Conferences Originally Scheduled for 990623.SSS Conference Rescheduled for 990712 & Ice Condenser Conference Rescheduled for 990720 ML20196A5781999-06-14014 June 1999 Discusses Notice of Enforcement Discretion for Duke Energy Corp Re Catawba Nuclear Station Unit 1 TSs 3.5.2 & 3.7.12 ML20195E9171999-06-0303 June 1999 Confirms Conversation with Bradshaw on 990526 Re Rescheduling 990607 Predecisional Enforcement Conference to Discuss Apparent Violation in Insp Repts 50-413/99-10 & 50-414/99-10.Conference Will Be on 990623 in Atlanta,Ga ML20195F4141999-06-0202 June 1999 Forwards Insp Repts 50-413/99-11 & 50-414/99-11 on 990422-23 & 0503.Apparent Violation Identified & Being Considered for Escalated Enforcement Action.Violation Involved Failure to Maintain Unit 1 Ice Condenser Lower Inlet Door Operable ML20207D0671999-05-20020 May 1999 Informs That During Meeting on 990512,arrangements Modified for Administration of Licensing Exams at Catawba Nuclear Station During Weeks of 990524 & 0607,respectively ML20207C8721999-05-20020 May 1999 Forwards Insp Repts 50-413/99-02 & 50-414/99-02 on 990314-0424.Three Violations Occurred & Being Treated as non-cited Violations.Activities Generally Characterized by Safety Conscious Operations & Sound Engineering & Maint ML20207C8061999-05-19019 May 1999 Confirms 990510 Telcon with R Jones Re Predecisional Enforcement Conference Requested by NRC & Scheduled for 990607 in Atlanta,Ga to Discuss Apparent Violation Associated with Potential Inoperability of SSS ML20207C7761999-05-19019 May 1999 Informs That on 990618,NRC Will Meet with Mgt of Duke Energy Corp to Discuss Performance of Catawba Facility & Extends Invitation to Attend Meeting as Observer ML20206P4911999-05-14014 May 1999 Forwards Safety Evaluation Accepting GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20206M4201999-05-11011 May 1999 Informs That NRC Ofc of Nuclear Regulation (NRR) Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt (DLPM) Created.Reorganization Chart Encl ML20206U4091999-05-10010 May 1999 Forwards Insp Repts 50-413/99-10 & 50-414/99-10 on 990314-0424.One Violation Occurred & Being Considered for Escalated Enforcement Action Involving Inoperability of Standby Shutdown Sys from 981216-29 ML20206N4191999-05-0606 May 1999 Informs That Team Will Inspect Dam at Standby Nuclear Service Water Pond on 990609.Purpose of Insp Will Be to Confirm That Structure Conforms with Design Documents & Capability of Performing Design Functions ML20205S5491999-04-21021 April 1999 Forwards SE Discussing DPC Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions. Response Acceptable ML20206B7941999-04-16016 April 1999 Confirms 990331 Telcon Between M Purser of Util & R Franovich of NRC Re Public Meeting Scheduled for 990618 in York,Sc to Discuss Results of NRC Recent Plant Performance Review for Catawba Nuclear Station ML20205N3471999-04-12012 April 1999 Forwards Safety Evaluation & Eri/Nrc 95-506, Technical Evaluation Rept on Submittal Only Review of IPE of External Events at Catawba Nuclear Station,Units 1 & 2 ML20205T3491999-04-0909 April 1999 Informs That on 990317,T Beedle & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Catawba Nuclear Station for Y2K.No Y2K Exam Scheduled.Initial Exam Requested for Apr 2001 for Approx 18 Candidates ML20205N0531999-04-0606 April 1999 Forwards Insp Repts 50-413/99-01 & 50-414/99-01 on 990124-0313.DPC Conduct of Activities at Catawba Facility Generally Characterized by Safety Conscious Operations & Sound Engineering.Five Violations Noted & Treated as NCVs ML20196K9961999-03-30030 March 1999 Forwards Synopsis of NRC OI Completed Rept Re Alleged Compromise of Initial Licensed Operator Exam at Cns.Oi Did Not Substantiate Allegation That Initial Operator Exam Compromised.Plans No Further Action Re Matter ML20205M2651999-03-25025 March 1999 Discusses PPR Completed 990201.Advises of Planned Insp Effort Resulting from Catawba PPR Review.Forwards Plant Issues Matrix & Insp Plan ML20207L7741999-03-15015 March 1999 Requests That NRC Exercise Discretion Not to Enforce Compliance with Actions Required by Plant,Units 1 & 2 Re TS Limiting Conditions for Operation 3.3.7 & 3.3.8 ML20207M9091999-03-0505 March 1999 Informs That Info Submitted by Application, Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20207A5821999-02-17017 February 1999 Forwards Insp Repts 50-413/98-12 & 50-414/98-12 & Notice of Violation.One Violation Being Considered for Escalated Enforcement Action ML20203G5161999-02-0505 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 990407. Representative of Facility Must Submit Either Ltr Indicating No Candidates or Listing of Candidates for Exam ML20203A2421999-02-0505 February 1999 Forwards SE Accepting Proposal to Revise Methodology in TR DPC-NE-3002-A,to Permit Use of single-node Model,Instead of multi-node Model,To Represent SG Secondary Sys for post-trip Phase of Loss of Normal Feedwater Analysis for Plant,Unit 2 ML20202J4751999-01-29029 January 1999 Responds to Concern Raised on 981020 Re Appropriateness of Interaction of NRC Headquarters Operations Officer with on-shift Operations Staff During Event ML20202C2511999-01-27027 January 1999 Forwards Request for Addl Info Re Util 980331 Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, for Catawba Nuclear Station. Response Requested within 60 Days of Date of Ltr 1999-09-24
[Table view] |
Text
..- . . . - . . _ - . - - - - . . - . - . . .
l (Hrhe 30,1996 Duke Power Company :
ATTN: Mr. W. R. McCollum Site Vice President '
Catawba Site '
4800 Concord Road York. SC. 29745-9635 t
SUBJECT:
MEETING SUMMAPY - CATAWBA This refers to the management meeting conducted in the Region II Office on October 23. 1996. The purpose of the meeting was to discuss the welding program. A list of attendees and a copy of your slides are enclosed.
In-accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2.
Title 10. Code of Federal Regulations, a copy of this letter and its s enclosures will be placed in the NRC Public Document Room.
(
! Should you have any questions concerning this lette , plea e contact us.
L Sincerely ;
l l
! Harol 0. C ristensen. Chief Main nanc Branch Divi ion o Reactor Safety ;
1 l Docket Nos.: 50-413 and 50-414 l License Nos.: NPF-35 and NPF-52 i i
l .
Enclosures:
- 1. List of Attendees l 2. Licensee Slides cc w/encls:
l M. S. Kitlan l Regulatory Compliance Manager l Duke Power Company 4800 Concord Road York, SC 29745-9635 Paul R. Newton Legal Department (PB05E)
Duke Power Company
- 422 South Church Street ;
l Charlotte, NC 28242-0001 l (cc w/encls cont'd - See page 2)
[
9611050239 961030 PDR ADOCK 05000413 P PDR _
l
l 4
DPC 2 (cc w/encls cont'd) i Robert P. Gruber :
Executive Director !
Public Staff - NCUC P. O. Box 29520 i Raleigh. NC 27626-0520 J. Michael McGarry. III, Esq.
Winston and Strawn 1400 L Street. NW ,
Washington. D. C. 20005 l North Carolina MPA-1 i Suite 600 l' P. O. Box 29513 Raleigh NC 27626-0513 Max Batavia Chief Bureau of Radiological Health
- S. C. Department of Health '
- and Environmental Control 2600 Bull Street Columbia. SC 29201 1
! Richard P. Wilson. Esq.
Assistant Attorney General S. C. Attorney General's Office P. O. Box 11549 Columbia. SC 29211 Michael Hirsch Federal Emergency Management Agency 500 C Street. Sw. Room 840 -
Washington D. C. 20472 i North Carolina Electric
. Membership Corporation l P. O. Box 27306 Raleigh. NC 27611 i
Karen E. Long l Assistant Attorney General N. C. Department of Justice l P 0. Box 629 Raleigh. NC 27602 Saluda River Electric Cooperative. Inc.
P. O. Box 929 Laurens. SC 29360 (cc w/encls cont'd - See page 3)
i DPC 3 (cc w/encls cont'd)
Peter R. Harden IV Account Sales Manager Power Systems Field Sales Westinghouse Electric Corporation ,
P. O. Box 7288 '
Charlotte. NC 28241 ,
County Manager _of York County ;
York County Courthouse York. SC 29745 i Piedmont Municipal Power Agency 121 Village Drive Greer. SC 29651 >
G. A. Copp Licensing - EC050 Duke Power Company ;
P. O. Box 1006 '
Charlotte. NC 28201-1006 T. Richard Puryear Owners Group North Carolina Elbctric Membership Corporation 4800 Concord Road York. SC 29745 Distribution w/encls:
P. Tam. NRR !
R. Carroll. RII l R. V. Crlenjak. RII N. Economos. RII R. Baldwin. RII G. Hallstrom. RII PUBLIC NRC Resident Inspector U.S. Nuclear Regulatory Commission 3 4830 Concord Road ;
York. SC 29745 l SEND TO PUBtIC DOCUMENT R00M7 YES NO 0FFICE RII:DRS RII:0RP RII:0RP SI"#
h f,V NAME NEcoomos:f tj RCarroll LWert DATE 1A/ D % 11/ b / % 10 / h / % -
10 / /% 10 / /% 10 / /%
i COPY? fES) NO (Y[M 'NO YES (IiO) YES NO YES NO YES NO UttACIAL RLMIRD COPY DOCUMENT NME: P:\ CATAWBA.M5M l
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LIST OF ATTENDEES Nuclear Reaulatory Commission S. Ebneter. Regional Administrator. Region II (RII)
Johns P. Jaudon. Acting Deputy Director. Division of Reactor Projects (DRP).
RII H. Christensen. Chief. Maintenance Branch (MB). Division of Reactor Safety (DRS). RII L. Wert. Acting Branch Chief. Branch 1. DRP H. Berkow. Director. Project Directorate Il-2. Office of Nuclear Reactor Regulation (NRR)
V. Nerses. Licensing Manager. II-2. NRR N. Economos. Reactor Engineer. MB. DRS M. Sykes. Resident Inspector. Branch 1. DRP Duke Power Comoany T. C. McMeekin. Vice President. MNS. DPC M. R. Robinson. DPC M. S. Sills. Site Manager. DPC G. Hallman. SGRP Overall Manager. DPC J. Grogan. Vice President, ESS. DPC M. Tuckman. Senior Vice President. DPC T. McConnell. Station Support Manager. DPC A. Grunsky. Service Manager. DPC S. VanMalsser. Work Management. DPC I
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4 ENCLOSURE 1
I , -M.
l Duke Power Company l WELDING PROGRAM i
Steam -h -
Replacement Generator Project
~
Nuclear Generation Department October 23,1996 HQDUE2
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Agenda ;
+ Introductory Remarks (:MST)
+ Catawba SGRP Experience (WR:M)
+ Welding Program Improvements (TL:M)
+ :McGuire SGRP Plans (TC:M)
+ Summary (TC:M)
+ Adjourn 2
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Introductory Remarks l
+ Introduction
+ Purpose of this Meeting
+ Current State
+Cause ;
+ Corrective Actions l
3
Introduction
+ Catawba SGRP the largest project since construction
+ Pleased with all project aspects except secondary welding
+ NRC and Duke identified issues with SGRP secondary welding
+ Duke has identified issues with our overall welding program
+ We've taken actions to improve overall welding program and McGuire SGRP 4
e, '.
l Purpose of Meeting
+ Describe Catawba SGRP welding issues and actions taken
+ Describe Duke welding program and
- actions to be taken
+ Describe how we will make McGuire SGRP secondary welding successful 5
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Present State
+ Our corporate welding program is in t need of improvement
+ Catawba SGRP project management did not adequately plan for secondary welding
+ Oconee is in outage and McGuire SGRP is near term 6
e s 'a i
Cause t
+ SGRP management failed-to recognize the deficiencies in the corporate welding program and drive improvements
+ The effectiveness of our corporate welding program had been slowly eroding over time 7 ,
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I Cause Details
+ SGRP Project management
-Inadequate readiness assessment in this area (8 other readiness assessments conducted)
-Inadequate technical support l vPlanning phase missed secondary weldmg issues as area of potential concern (over-confidence) ,
vMissed significance of pre-outage pre-fab indicators in execution phase 8 l
Cause Details i
+ Corporate Welding Program
-Lack of ownership of corporate program
-Qualification vs Skill Inadequately focused weld tech support 9 i i
.. . j k
Corrective Actions
+ Completed Catawba welding
- All welds are acceptable and meet code
+ Implement Corporate Welding Team recommendations i
+ Specific action plan to ensure McGuire success ,
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10 4
I Catawba SGRP Experience Bill.McCollum 11
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _________-___-_--J
Catawba SGRP Experience l
+ Welding Plan Primary Side ;
-Secondary Side
+ Pre-Fab Results & Response
+ Field Problems & Response
+ Summary i
12 ;
Welding Plan - Primary Side
+ Reactor coolant pipe - 8 welds, approx. 2.5" wall, 36" OD, stainless steel ,
+ Welding on or near critical path for the outage
+ Potential high dose job .
+ Narrow gap automated welding process selected for .
- Significant reduction in volume of weld metal
- Less shrinkage
- Reduced duration
- Excellent results in other plants 13
s 0, e
Welding Plan - Secondary Side -
+ Pre-fab
- 46 butt welds ,16" to 3"
- Approx 200 socket welds ,2" and less
+ Field welds
- 82 butt welds,34" to 3"
- Approx 200 socket welds ,2" and less
+ Considerations for the plan
- Range of sizes and space limitations
- Types of welds not dissimilar to welding performed in past
- Off critical path 14
9 Welding Plan - Secondary Side
+ Planned all secondary side welding with manual processes
, -Main feedwater reroute was the largest welding scope Planned pre-fab to serve as verification of plan for field welding 15
% L SGRP Pre-Fab Butt Welds i
30 25 --
us 32 20 - -
hO 15 --
10 -- l
.O 1 E 5- -
5 0 I I Main Layup Aux Feedwater Feedwater s No repairs m One or more repairs
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Pre-Fab Results
+ Pre-fab problems were with root pass on CrMo feedwater piping
+ No significant reject issues with other welds
+ Feedback from welders indicated TIG filler material problem 17
%e Response to Pre-Fab Problems
+ Evaluation of filler and base material
+ Searched for alternate filler material
+ Tested non-qualified filler material
+ Success rate improved
+ Decision to proceed with existing filler material based on improvement during pre-fab 18
Field Successes
+ All auxiliary feedwater nozzle welds and 12 in-line welds were completed with no repairs
+ Socket welds completed with no rejects 19
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Field Problems i
+ Problems with preheat practices
+ Difficulty with feedwater CrMo Root pass problems similar to pre-fab
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+ Problems with dissimilar metal i INCONEL nozzle welds, (Blowdown and Layup) 20
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SGRP Field Butt Welds 30 i 25 - -
20 - -
15 -- !
10 - -
0 l i I I i Reactor Main Main Aux Blowdown Layup Coolant Steam Feedwater Feedwater E No repairs MOne or more repairs
Response to Field Problems
+ 8/9/96 - SGRP welding work stopped in response to problems identified with preheat practices
- Reviewed preheat practices and provided additional guidance for welders
- Timeout discussion with welders and QC inspectors to review preheat guidance
- Increased QC random in-process inspections
- Stopped torch preheat & developed procedure on preheat practice 22 i
so 'e Response to Field Problems
+ 8/12/96 - Brought in experienced weldmg engineer as issue manager for SGRP welding problems
+ Site management chartered independent assessment of SGRP welding program (Experienced QC Manager, Outside l Welding Consultant, Experienced Welding Tech Support Personnel) 23
l .. .
1 Response to Field Problems l
l + Independent Assessment Results
-Specific knowledge of process specifications and other program requirements need improvement
-Details of QC inspection practice varied between inspectors
-Less automated welding used compared to other projects of this magnitude .
u
e Response to Field Problems i
+ Independent Assessment Results
- 3_eed for greater management oversight vplanning vincreased technical support vmore technical content in pre-job briefings
- All Code, QA and procedure ,
requirements were being met 25
ta
- V Response to Field Problems
+ Beginning 8/12/96 - Focused additional weldmg expertise (Duke and Consultant) to develop solutions to reject issues
- Reviewed INCONEL and CrMo problems and developed additional guidance on joint preparation and welding technique
- Enhanced technical content of pre-job briefings for welders
- Reviewed welding problems with four outside welding contractors to gain benefit of their experience 26
i Response to Field Problems ;
+ Week of 8/19/96 ,
- Revised pipe layout for 3" INCONEL nozzles to add spool piece allowing access for surface prep of the ID of the root pass
- Revised welding plan for remaining INCONEL nozzle welds i
vChanged to use of " slope control" welding machines VInstituted mock-up practice 27 t
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Response to Field Problems 1 ,
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+ Week of 8/26/96 Brought in additional Duke and specialty welding contractors with .
INCONEL experience
+ Week of 9/2/96
-Located different TIG filler material for CrMo pipe 28
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Summary
+ More problems occurred than anticipated with secondary welding .
a Recognized significance
-Responded to correct weld process 1ssues Attacked reject issues using all available expertise and resources l 29
e NGD Welding Program Improvements Tony McConnell
NGD Welding Program Improvements l
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+ Current State Program Deficiencies
+ How Did This Happen?
t
+ Corrective Action Plan
+ Our Vision for the Future
+ Sustaining High Quality 31 t I
_ _ _ _ ______J
Current State Program Deficiencies i
+ Primary Deficiency Lack of overall welding program :
ownership ;
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32
Current State Program Deficiencies
+ Secondary Deficiencies
- Unclear roles & responsibilities
- Inconsistent processes and practices
- Inadequate utilization of knowledgeable welding support personnel 1
- Lack of recognition that welding skills had eroded
- QA audits focused primarily on code / program compliance versus performance 33
- s. *e l.
How Did This Happen? ,
+ Reduced new construction coupled i
with multiple reorganizations resulted .
in inadequate attention to our welding program i
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t 34
tn
- e Corrective Action Plan t
+ Establish Clear Program Ownership
-Re-establish overall Departmental ownership by assigning a NGD lead l
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Welding Program Ownership NGO Station Support Organization Tony McConnel Welding Program Owner WeMi@ dig NGD General Office ----
Group Morris Sample i ;
t Site Maintenance ESS Organization i Organization i
I r I '
t 8
i i S e Maintenam her &
Section IX Program Owner ----------- 8------------ Technical Support (Test Shop & Met Lab) ,
i Key:-- Welding Program interface OrganizationalInterface 36 :
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i Corrective Action Plan l
+ Establish Clear Roles & Responsibilities Clarify site roles & responsibilities and strengthen site ownership Document each organization's roles &
- responsibilities, the welding process and organizational interfaces in our Corporate and/or Departmental Welding Manuals 37
Corrective Action Plan
+ Develop Consistent Processes ,
- Consolidation of site welding manuals into a single .
departmental welding manual
- Formation of a group at each site responsible for .
welding whose functions will include: ,
v weldability/constructability reviews y mock-up training requirements v inspecti,1 requirements y review of rejected welds and repair decisions
- Incorporation of more independent reviews into the procedure qualification process 38
Corrective Action Plan
+ Assure utilization of qualified and knowledgeable personnel
- Qualifications for performing technical support functions will be documented
- Assessments will be performed for technical support personnel and training plans established to address any knowledge level weaknesses '
- Welding program and process training will be provided for all welders
- All personnel performing visual inspections of non safety related 1 B31.1 pressure piping welds will be trained to ASNT Level II or l equivalent
- QC Inspectors will be re-trained to ensure consistency of inspections 39 '
e Corrective Action Plan
+ Recognize that welding skills must be l maintained
- Will institute a limited access testing requirement for all-process piping welders
- Will require annual Jaegar eye exams for all process piping welders
- Will ensure welder proficiency levels are maintained
- High level welding expertise will be available via GO and ESS program owners for complex problem solving 40
ss e e
Our Vision for the Future .
Focused Skilled Quality
+ =
Product Program Workforce
+ Implementation of these corrective actions will strengthen our existing program to achieve this vision
+ Significant corrective actions will be completed by mid 1997
+ A transition team has been formed to implement corrective actions (Steve Sills is the Team Leader) 41 i
Sustaining High Quality l + Periodic self assessments will be performed to determine our welding program effectiveness
, + The Welding Working Group will be the forum to identify continuous improvement efforts
+ Key program indicators will be defined, tracked and trended 42
McGuire SGRP Plans Ted McMeekin 43
l MNS SGRP Improvement Plan
+ Alignment with Corporate Welding Initiatives
+MNS SGRP Welding Scope
+ Weld Planning and Technical Support
+MNS SGRP Welding Direction
+ Project Management Initiatives 44
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Alignment with Corporate Welding Initiatives
+ Corporate welding initiatives will be implemented by mid 1997
+ Corporate welding initiatives that will be in place at MNS prior to 1EOC11
- MNS Maintenance assigned ownership and responsibility for all site welding effective immediately
- MNS welding manual revised to define changes .
specified by the Corporate Welding Initiative
-Roles and responsibilites defined l
-Minimum qualifications listed 45
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MNS Welding Program OrganizationalInterface NGO Station Support Organization Tony McConnel Welding Program Owner Welding Working NGD General Office ----
Group Morris Sample i
l Site Maintenance MNS SGRP Weld TS ESS Organization i Organization ---
Steve Van Maissen e Mano Nazar i
I I
I Site Maintenance Owner &
Section IX Program Owner ----------- 8------------ Technical Support (Test Shop & Met Lab)
Greg Holbrooks Key: --- Welding Program Interface .
OrganizationalInterface 46 i
MNS Welding Scope
+ Primary System (Reactor Coolant)
- MNS same as CNS scope v8 NC Welds
+ Secondary System (wet layup, blowdown, auxiliary feedwater, main feedwater, and main steam)
VButt welds: 60-65 field & 60-65 shop
-25% reduction in field butt welds from CNS VSocket welds: ~ 200 field & 200 shop 47
Weld Planning andTechnical Support
+A detailed plan will be developed for each group of similar welds including:
vDetermination of best welding process l (automatic, manual, TIG, etc) vWelder qualification and training requirements 1 vSpecify welders based on skill vIdentification of appropriate welding filler materials vApproach to weld pre-heat and post weld heat treatment 48
Weld Planning and Technical Support
+ To build this plan, the MNS SGRP has employed fulltime welding technical support to: .
YProvide leadership for detailed weld planning including material identification, equipment selection and specification, and training related issues .
YProvide technical assistance and execution support '
to SGRP on all welding issues and adjust plan as required ;
VServe as main link between SGRP and Station Welding Owner VProvide guidance for continuous improvement to welding plan, lessons learned process, and preparation for next SGR outage 49
ee **
MNS SGRP Welding Direction vPrimary System Welds Narrow gap automated process (same as CNS)
-Will utilize the same vendor (FTI) 50
. . .. l MNS SGRP Welding Direction l
l + Secondary System Welds vUse automated technology to extent i practical vUse internal workforce to support both .
automated and manual welding vEmploy outside technical expertise to support automation vPerform nozzle to process pipe dissimilar welds as part of SG prep activities .
TUse resistance heating for all pre-heat requirements 51
MNS SGRP Welding Direction
+ Execution Workforce Training y Limited access welding test for welders assigned to pressure piping y Provide detailed hands-on and classroom training for new equipment, material, or process changes y Perform mock-up training to evaluate technique, ,
skill level, and proficiency of workforce y Provide detailed, technical guidance and instruction in pre-job briefs y Perform Jaegar eye exams for all process piping welders y QC inspectors will undergo refresher training to ensure consistency 52 .
Project Management Initiatives
+ NSD 604, stop work directive will be emphasized to all SGRP and associated station groups
+ Establish clear success criteria for welding and contingency plans should problems occur
+ Perform independent assessment of MNS SGRP welding plan 53
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Summary
+ Improve corporate welding program
+ Develop detailed MNS welding plan
+ Perform independent assessment of MNS welding plan l
+ As a result of Catawba's experience we anticipate a smooth and predictable SGRP at McGuire
-We do not take Catawba's experience for granted 54
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