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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] Category:SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE
MONTHYEARIR 05000413/19970991997-06-0404 June 1997 SALP Repts 50-413/97-99 & 50-414/97-99 for Period 951008- 970426 IR 05000413/19930201993-11-17017 November 1993 Discusses SALP Insp Repts 50-413/93-20 & 50-414/93-20 on 920503-931002.Informs That Overall Performance at Plant Improved Since Previous Assessment IR 05000413/19880241988-10-13013 October 1988 SALP Repts 50-413/88-24 & 50-414/88-24 for Aug 1987 - Jul 1988 IR 05000413/19850421985-12-19019 December 1985 App to SALP Repts 50-413/85-42 & 50-414/85-44 ML20138Q7311985-12-19019 December 1985 SALP Repts 50-413/85-42 & 50-414/85-44 for Mar 1984 - Sept 1985 1997-06-04
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Inspection Report - Catawba - 1993020 |
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hbV 171993 Docket Nos. 50-413, 50-414 License Nos. NPF-35, NPF-52 Duke Power Company ATTN: Mr. D. L. Rehn Site Vice President Catawba Site 4800 Concord Road York, SC 29745-9635 Gentlemen:
SUBJECT: SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE (NRC INSPECTION REPORT NO. 50-413/93-20 AND 50-414/93-20)
The NRC Systematic Assessment of Licensee Performance (SALP) has been completed for your Catawba facilit The facility was evaluated for the period May 3, 1992 through October 2, 1993. The results of the evaluation are documented in the enclosed SALP Report. This report will be discussed with you at a public meeting to be held at the Catawba facility on November 29, 1993, at 1:00 The performance of your Catawba facility was evaluated under the revised SALP process implemented by the Nuclear Regulatory Commission on July 19, 199 Performance was evaluated in the functional areas of Plant Operations, Maintenance, Engineering, and Plant Suppor Overall performance at Catawba has improved since the previous assessmen Management's attention to plant safety resulted in very good control of plant activities and good monitoring of plant equipment performance trends. The Plant Support area was evaluated as superior while Plant Operations, Maintenance, and Engineering were evaluated as goo Your safety assessment programs for identifying and correcting problems were effective in certain area The active role of management was noteworthy in making improvements in configuration control in the second refueling outage. Continuing efforts to improve your work control process were noted, including the use of your Independent Plant Evaluation to identify risks during outages and appropriately schedule wor Two areas of continuing weakness indicate that additional management focus is necessary to achieve sustained performance improvements. Your initial and requalification training program for licensed operators remained at a marginally satisfactory level without significant improvement over the previous assessment period. Additionally, procedure adherence issues were noted as a problem in three functional areas: Plant Operations, Maintenance and Engineering. Procedure adherence had also been identified in the previous SALP as a problem in the Maintenance / Surveillance area. Your attention is directed toward these challenges in the licensed operator training program and 9312140065 931117 #
PDR ADOCK 05000413 ;
G ppg M4D 1
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Duke Power Company 2 NO\/171993 i
in your programs for procedural adherence. These require additional management ,
attentio Any comments you have concerning our evaluation of the performance of your Catawba facility should be discussed at the public meeting and should be i submitted in writing to this office within 30 days after the meetin
Sincerely,
'. Y &
Stewart D. Ebneter Regional Administrator Enclosure:
SALP Report l
cc w/ encl:
R. C. Futrell ,
Compliance :
Duke Power Company 4800 Concord Road ,
York, SC 29745-9635 l l
A. V. Carr, Es !
Duke Power Company 422 South Church Street Charlotte, NC 28242-0001 J. Michael McGarry, III, Es Winston and Strawn 1400 L Street, NW Washi" .on, D. C. 20005
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North Carolina MPA-1 Suite 600 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 cc w/ encl: See page 3
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, cc w/ encl: Continued Richard P. Wilson, Es 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 North Carolina Electric Membership Corporation P, O. Box 27306 Raleigh, NC 27611 Karen E. Long Assistant Attorney General N. C. Department of Justice P. O. Box 629 Raleigh, NC 27602 Saluda River Electric Cooperative, In P. O. Box 929 Laurens, SC 29360 T. Richard Puryear Nuclear Technical Services Manager Carolinas District Westinghouse Electric Corporation 2709 Water Ridge Parkway, Ste. 430 Charlotte, NC 28217 County Manager of York County York County Courthouse York, SC 29745 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 INPO
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Duke Power Company 4 NOV 171993 ;
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Chairman Selin Commissioner K. C. Rogers Commissioner F. J. Remick Commissioner E. G. de Planque ,
J. M. Taylor, EDO .
J. Lieberman, OE '
J. F. Plisco, Regional !
Coordinator, ED0 .
T. E. Murley, NRR -
L. J. Callan, NRR 5. A. Varga, NRR F. Allenspach, SALP Coordinator, NRR ,
Regional Administrators, RI, RIII l RIV, and RV !
.. A. Reyes, RII E. W. Merschcff, RII !
J. R. Johnson, RII A. Julian, RII i A. Peebles, RII E. Cline, RII .
- M. Collins, RII M. B. Shymlock, RII J. J. Blake, RII
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L. L. Lawyer, RII W. H. Rankin, RII l T. Decker, RI; r K. P. Barr, RII .
D. R. McGuire, RII A. R. Herdt, RII l M. S. Lesser, RII r R. L. Watkins, RII .
R. J. Freudenberger, RII K. M. Clark, RII l FEMA i
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Chairm n Selin Commissipner K. C. Rogers ;
Commissioper F. J. Remick ;
Commissiorier E. G. de Planque :
J. M. Tayloh, EDO ;
J. Lieberman,\0E !
J. F. Plisco, Regional l Coordinator, ED0 '
T. E. Murley, NRR !
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S. A. Varga, NPR F. Allenspach, SALP Coordinator, NRR i Regional Administrators,MI, RIII !
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L. A. Reyes, RII : W. Merschoff, RII ' R. Johnson, RII A. Julian, RIl A. Peebles, RII , Cline, RII Collins, RII
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T. Decker, RII K. P. Barr, RII i D. R. McGuire, RII !
A. R. Herdt, RII !
M. S. Lesser, RII l R. L. Watkins, RII ;
R. J. Freudenberger, RII i K. M. Clark, RII ;
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SALP REPORT - CATAWBA NUCLEAR STATION ;
50-413/93-20 and 50-414/93-20 ; BACKGROUND ,
l l The SALP Board convened on October 19, 1993, to assess the nuclear :
safety performance of Catawba, Units 1 and 2, for the period May 3, l 1992, through October 2, 1993. The Board was conducted pursuant to NRC
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Management Directive 8.6, " Systematic Assessment of Licensee Performance." Board members were Jon R. Johnson, (Chairperson) Deputy Director, Division of Reactor Projects (DRP), RII; Johns P. Jaudon, Deputy Director, Division of Reactor Safety (DRS), RII; Bruce Mallett, Deputy Director, Division of Radiation Safety and Safeguards (DRSS), RII; and David B. Matthews, Director, Project Directorate II-3, Office of Nuclear Reactor Regulation (NRR). !
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II. PERFORMANCE ANALYSIS - PLANT OPERATIONS ,
This functional area consists of the control and execution of activities directly related to operating the facility. It includes activities such l as plant startup, power operation, plant shutdown, and response to ,
transients. It also includes all activities related to initial and requalification training programs for NRC licensed operator Duke Power Company's attention to operational safety. resulted in a good l level of performance. Corrective actions taken by station management as 1 well as the operations staff were very effective in improving ;
performance during the Unit 2 refueling outage. Weaknesses in controlling the proper configuration of plant equipment had continued ;
into the first half of this asse::sment period. Most of these were caused by personnel errors, improper use of tagouts, and system lineup !
procedures during a refueling outage on Unit 1. Procedures were revised for maintaining containment integrity, and training was held regarding-block tagouts and valve lineup proce-dures. Management focused {
attention on these areas, and assignments were made to specific !
individuals on shift to be responsible for certain operational functions I such as containment closure. As a result, no significant tagout or configuration control problems occurred during the Unit 2 outag !
l Station management was very effective in review of refueling outage ;
schedules in order to minimize risk during shutdown periods. The time j that the reactor coolant system was in mid-loop condition has been minimized through planning and scheduling as well as through techniques such as vacuum vent and fill of the reactor coolant system at the completion of the outage. Of special note was the use of a temporary diesel generator as a backup source of power for decay heat removal system The operations staff exhibited effective teamwork and was active in I addressing the root cause of plant operational issues by discussions in l l
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the form of a quality improvement team. They have received quality ,
improvement or " excellence" training and have participated in recommending solutions to improve operator monitoring equipment such as modifications to the diesel generator annunciator panel and the emergency safeguards feature bypass panel. Operators have also visited other power plants for bench marking and have initiated improvements in -
tagging, lateling, and reduced the number of lit annunciator ,
Catawba operations management did not always maintain proper oversight and plant operational performance was challenged by procedural adherence and weaknesses in plant system knowledge. Lack of adequate system j knowledge and inadequate referral to the appropriate alarm response i procedure resulted in operation of a coolant charging pump without a i suction path. Improper procedure adherence and coordination also resulted in a failure to drain the fuel transfer canal prior to removing ,
the blank flange. In addition, subsequent to improper operator response :
to an RHR system piping failure, the licensee's self assessment did not identify this as a performance weaknes '
Management did not focus sufficient attention on initial and requalification licensed operator training program performance proble Weaknesses were observed in procedural use, crew communications, observation of control board indications, and attention to detail. A significant number of examination failures occurred, and the requalification program was judged marginally satisfactory for the third time in a row, indicating lack of progress in correcting these performance problems. During the most recent requalification i examination in May, 1993, deficiencies continued to be observed in the -
formality of communications and non-emergency procedural adherenc Steps taken to improve the operator training program included revision ;
to the Emergency Operating Procedures (to bring them in conformance with !
the Westinghouse Owners Group guidelines), management observations of :
licensed operator training in the simulator, and assignment of an i operations staff member to direct licensed operator training. The !
continuing problems in this area indicate a need for management to focus ,
attention in this are l
The Operations area is rated Category l
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III. PERFORMANCE ANAL.YSIS - MAINTENANCE i This functional area addresses those activ! ties related to diagnostic, predictive, preventive and corrective maintenance of plant structures, systems, and components. It also includes the conduct of surveillance !
testing activities, inservice inspection and testing, and special tests. i Sood overall performance in the maintenance of plant equipment resulted in improving trends in the number of plant transients. Management ;
oversight of field activities improved but needs to continue. This ;
improvement is attributed to the extensive upgrades to the mechanical !
maintenance and instrumentation procedures and to various licensee l
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initiatives to improve personnel performance. Bu u'servations u indicate that additional oversight is needed to assure proper implementatio Examples included: failure to follow a diesel generator load sequencer calibration procedure, which resulted in the blackout of the Unit 2 train B emergency bus; and failure to follow procedures for safety injection pump motor bearing maintenance, resulting in motor failur Maintenance training programs were well supported. The maintenance area was adequately staffed with knowledgeable and skilled personnel. The licensee's corporate level training for maintenance personnel addressed generic areas such as team building managerial and supervisory skills, and communication skills, as well as ;ompany goals and policies. During this assessment period the licensee has continued to use mock-ups in its training program. These now include mock-ups for the emergency diesel, valves, valve motor operators, breakers and relays and the steam generator lower head regio Excellent plant material condition and superior housekeeping demon-strated strong management support and attention. Leaks have been anticipated and directed to appropriate collection points resulting in a small amount of contaminated area thus facilitating ready access for plant operations, surveillance and maintenanc Improvement was made in the quality of maintenance procedure The licensee continued with an initiative to upgrade instrumentation and control procedures. Although this effort is not scheduled to be i complete until late 1996, a major milestone has beea reached in that the ;
two of three higher priority categories have been complete '
Planning and scheduling for outages improved during this period. A Unit I refueling outage was extended in September 1992 due to leaking conoseals and the need for repairs to establish correct reactor coolant pump seal leakoff flow. A subsequent Unit 2 refueling outage was completed four days ahead of schedule with minimal need for rewor This outage included the major tasks of moisture separator reheater tube bundle replacement and replacement of numerous large nuclear service water system valves. The valve replacement reflected good preplanning i and good cooperation / coordination among the various groups involve Overall, this Unit 2 outage was one of the most effective done at Catawba. The January 1993 repair of the control room ventilation chiller compressor motor and the June 1993 replacement of the Unit 1 service water piping to the containment ventilation units were also accomplished in a well controlled manner with good coordination between the various groups involve Inservice inspection (ISI) activities early in the assessment period i reflected adequate management and control of the ISI program, and Nondestructive Examination examiners and procedures were of high qualit Steam generator eddy current testing analysis and tube i sleeving activities were generally thorough and detailed. Concerns with inadequate examination of a pulled steam generator tube plug weld in the :
Unit 1 outage in September 1992 were adequately correcte A later
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review of similar areas in February 1993 revealed no weaknesses in the implementation of the ISI program. The licensee continued to maintain an effective and conservative flow accelerated corrosion program to maintain high energy carbon steel piping systems within acceptable wall thickness limit ;
The Maintenance area is rated Category '
I PERFORMANCE ANALYSIS - ENGINEERING The functional area of engineering addresses the adequacy of technical -
and engineering support for all plant activities. Design contr'1 and i modifications are encompassed as are engineering and technical support -
for operations, for maintenance, for outages and for testin Engineering and technical support of day-to-day plant operations was i very good during this assessment period. Strengths in engineering :
support to the site included effective control of the engineering backlog, the ability to trend parameters and to identify problems, the consideration of risk as a factor in planning and sequencing work ,
activities, and the strong communications between engineering and operations, especially during plant testing and startup after outage Parameters that were trended and tracked by the licensee included steam i generator and service water system performance. Additionally, the
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i licensee provided comprehensive engineering response and strong technical expertise for issues regarding steam generator tube degradatio Station engineers demonstrated generally strong performance in correcting problems, such as a design inadequacy with the auxiliary feedwater controls (involving the interaction of non-safety-related equipment with safety-related control circuitry), the electrical distribution safety system functional inspection findings, and the significant problems uncovered in testing and maintenance of motor operated valves. The problems in this latter instance, inadequate control over torque switches, resulted in service water system 1 inoperability and escalated enforcemen !
Communications between reactor engineering and plant operators were inadequate early in the assessment period. In one instance, the computer program to calculate thermal power was not changed at the appropriate point in power ascension to reflect tempering flow to the .
steam generators and thereby to determine reactor power accuratel In the other instance, procedural steps associated with hot channel calculations were not completed correctly. These early instances indicated a potential problem with procedural adherence and inter-departmental communication ;
Technical support provided to licensing, as exhibited in docketed i submittals, was generally superior. The licensee's packages were ,
usually complete. In those instances when questions or discussions were ;
necessary, the licensee provided adequate technical information quickl l l
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While certain engineering and technical support self-assessment activities were viewed as improving or having a positive trend by the end of the assessment period, the licensee faced the challenge of resolving long standing issues such as service water system degradatio The Engineering area is rated Category PERFORMANCE ANALYSIS - PLANT SUPPORT i
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This functional area covers all activities related to plant support
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functions, including radiological controls, emergency preparedness,
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security, chemistry and fire protectio Throughout the assessment, the licensee e,.hibited strong performance in identifying and responding to plant support issues. Self-ascessment programs were performance-based and thoroug Responses to assessment findings and to events were technically sound, complete and timely. A significant contributor to this was the well qualified staff in all areas. The licensee did a superior job in addressing the challenge of procedural adherence problems noted during last assessment with no problems noted this tim Trending and analyzing data resulted in improvements in physical security assessment aids (e.g., image capture system and improved cameras) and contributed to examining methods for reducing radiation doses for individual groups. The use of electronic dosimetry was a good tool initiated to aid in tracking ways to reduce dose. There are challenges that were not resolved. Self-identified problems with access controls (i.e., unsecured vital area doors and misread security badge events) continued to be a significant portion of the licensee's loggable events. An excellent initiative was used to identify locations where the radiation source term exceeded the general area dose rates (i.e.,
hot spots); however, the licensee had not completed the necessary next step to reduce or eliminate the spot The licensee continued to be proactive in controlling contaminatio The continued reduction of the amount of contaminated areas was superior and improved accessibility to the majority of the plant. Also noteworthy were the steps such as use of drip bags to prevent potential recontamination of areas. Personnel contamination events were reduced from the previous assessment period even though the challenges were
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simila The ALARA program was good and supported by good communications between plant functional groups. This contributed to initiatives which reduced dose to personnel. Examples included use of mock-up equipment and pretraining for outages and chemical flushing during shutdown The radiological effluent monitoring and chemistry programs were effective in maintaining essential chemistry parameters and radiological releases well below regulatory limits. The licensee had improved the
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i availability of effluent monitors but continued to have some isolated l problems in this area. Some of these were self-identified (i.e., I failure to initiate grab samples when the turbine building sump l radiation monitor was declared inoperable and a number of malfunctions i in the equipment used for environmental monitoring). Another problem ,
was the licensee's failure to question a significant increase in the :
gaseous effluents as an adverse trend (subsequently determined to be l related to a measuring methodology change). Although this was.an ;
isolated case, it was an example of inattentio '
The emergency preparedness organization and management controls were j excellent in assuring timely completion of required tests and ;
surveillances. Performance during the annual emergency exercise in May ;
1993 was excellent with the exception of a single weakness. The :
licensee's staff had created a challenging scenario. Although there
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were some problems in the correctness of the anticipated emergency i classifications, exercise participants exhibited excellent capability to I analyze plant conditions and to identify and correct problems. The fire ,
brigade response was prompt and effective. Some minor problems with ,
emergency notification information continued; however, the licensee had corrected the problem of timely notifications identified during the '
previous assessment perio Emergency response facilities were well maintaine The Plant Support area is rated Category :
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