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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F8231999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of Catawba Nuclear Station.Based on Review,Nrc Did Not Identify Any New Areas That Warranted More than Core Insp Program Over Next Five Months.Historical Listing of Issues,Encl ML20217H0041999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217F1301999-10-0707 October 1999 Forwards Rev 1 to Request for Relief 99-03 from Requirements of ASME B&PV Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting (Vg) Sys ML20212J3011999-10-0101 October 1999 Forwards Exemption from Certain Requirements of 10CFR54.17(c) Re Schedule for Submitting Application for Operating License Renewal.Se Also Encl ML20217K2651999-10-0101 October 1999 Forwards Retake Exams Repts 50-413/99-302 & 50-414/99-302 on 990921-23.Two of Three ROs & One SRO Who Received Administrative Section of Exam Passed Retake Exam, Representing 75 Percent Pass Rate 05000414/LER-1999-004, Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments1999-09-27027 September 1999 Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments 05000413/LER-1999-015, Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept1999-09-27027 September 1999 Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept ML20217A7911999-09-24024 September 1999 Forwards Insp Repts 50-413/99-05 & 50-414/99-05 on 990718- 0828 at Catawba Facility.Nine NCVs Identified Involving Inadequate Corrective Actions Associated with Degraded Svc Water Supply Piping to Auxiliary Feedwater Sys ML20212E6471999-09-24024 September 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for Catawba NPP & 990615.Informs That NRC Reviewed Response for Catawba & Concluded That All Requested Info Provided.Considers GL 98-01 to Be Closed for Catawba ML20212F0941999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals for Cns,Units 1 & 2 ML20212M2001999-09-20020 September 1999 Confirms 990913 Telcon Between M Purser & R Carroll Re Management Meeting to Be Conducted on 991026 in Atlanta,Ga to Discuss Operator Licensing Issues 05000414/LER-1999-005, Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments1999-09-20020 September 1999 Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments ML20212D5321999-09-15015 September 1999 Informs That Duke Energy Corp Agrees to Restrict Max Fuel Rod Average Burnup to 60,000 Mwd/Mtu,In Order to Support NRC Final Approval & Issuance of Requested Amend ML20212B4641999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for Catawba Nuclear Station,Units 1 & 2 ML20212A4131999-09-14014 September 1999 Informs That TR DPC-NE-2009P Submitted in 990817 Affidavit, Marked Proprietary,Will Be Withheld from Public Disclosure, Pursuant to 10CFR2.709(b) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20212M1931999-09-13013 September 1999 Refers to 990909 Meeting Conducted at Region II Office Re Presentation of Licensee self-assessment of Catawba Nuclear Station Performance.List of Attendees & Licensee Presentation Handout Encl ML20212A3751999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementation Code Case for Duration of Insp Interval ML20212A5191999-09-0808 September 1999 Requests NRC Approval for Relief from Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,App VI,VI-2430(c) & 2440(b).Approval of 99-GO-002 Is Requested by 000301 05000413/LER-1999-014, Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment1999-09-0101 September 1999 Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment 05000414/LER-1999-003, Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev1999-08-31031 August 1999 Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev 0 of LER ML20211H1741999-08-30030 August 1999 Forwards Comments on Catawba Nuclear Station Units 1 & 2 & McGuire Nuclear Station,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid.Ltr Dtd 990107,rept ATI-98-012-T005 & Partial marked-up Rept WCAP-14995 Encl ML20211M4451999-08-30030 August 1999 Forwards Summary of Util Conclusions Re Outstanding Compliance Issue Re Staff Interpretation of TS SR 3.0.1,per Insp Repts 50-369/99-03 & 50-370/99-03,as Discussed with NRC During 990618 Meeting 05000413/LER-1999-013, Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER1999-08-25025 August 1999 Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER ML20211M8191999-08-25025 August 1999 Confirms 990825 Telcon Between G Gilbert & R Carroll Re Mgt Meeting to Be Held on 990909 in Atlanta,Ga,To Allow Licensee to Present self-assessment of Catawba Nuclear Station Performance ML20211A9641999-08-20020 August 1999 Forwards SE Authorizing Licensee 990118 Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section XI for Plant,Units 2 ML20211C1191999-08-18018 August 1999 Forwards ISI Rept Unit 1 Catawba 1999 RFO 11, Providing Results of ISI Effort Associated with End of Cycle 11 ML20211B9471999-08-18018 August 1999 Forwards Request for Relief 99-02,associated with Limited Exam Results for Welds Which Were Inspected During Unit 1 End of Cycle 11 RFO ML20211C3651999-08-17017 August 1999 Forwards Rev 25 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program, Which Includes Reformatting of Manual & Addl Changes as Noted in Attached Summary of Changes ML20211F2971999-08-17017 August 1999 Forwards non-proprietary & Proprietary Updated Pages for DPC-NE-2009,submitted 980722.Pages Modify Fuel Design & thermal-hydraulic Analysis Sections of DPC-NE-2009. Proprietary Page 2-4 Withheld,Per 10CFR2.790 05000413/LER-1999-011, Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment1999-08-16016 August 1999 Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment ML20211B1121999-08-16016 August 1999 Forwards Topical Rept DPC-NE-2012, Dynamic Rod Worth Measurement Using Casmo/Simulate, Describing Results of Six Drwm Benchmark Cycles at Catawba & McGuire & Discusses Qualification to Use Drwm at Catawba & McGuire ML20210V0321999-08-13013 August 1999 Forwards Insp Repts 50-413/99-04 & 50-414/99-04 on 990606- 0717.Six Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20210S2751999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl ML20210Q3751999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr as Listed,Thirty Days Before Exam Date,In Order to Register Individuals for Exam ML20210N9521999-08-0404 August 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual.Documents Constitutes Chapter 16 of Ufsar.With List of Effective Pages IR 05000413/19980131999-08-0202 August 1999 Discusses Integrated Insp Repts 50-413/98-13,50-414/98-13, 50-413/98-16,50-414/98-16 & NRC Special Repts 50/413/99-11 & 50-414/99-11 Conducted Between Aug 1998 & May 1999.Six Violations Occurred,Based on OI Investigation & Insp ML20210M6411999-07-29029 July 1999 Forwards Request for Relief 99-03 from Requirements of ASME Boiler & Pressure Vessel Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting Air (Vg) Sys 05000413/LER-1999-010, Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units1999-07-22022 July 1999 Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units IR 05000413/19990101999-07-22022 July 1999 Discusses Insp Rept 50-413/99-10 & 50-414/99-10 on 990314- 0424 & Forwards Notice of Violation Re Failure to Comply with TS 3.7.13,when Misalignment of Two Electrical Breakers Rendered SSS Inoperable from 981216-29 ML20217G5241999-07-20020 July 1999 Forwards Exam Repts 50-413/99-301 & 50-414/99-301 on 990524- 27,0603,07-10 & 16.Of Fourteen SRO & RO Applicants Who Received Written Exams & Operating Tests,Eight Applicants Passed & Six Failed Exam 05000413/LER-1999-009, Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept1999-07-19019 July 1999 Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept 05000414/LER-1999-001, Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed1999-07-15015 July 1999 Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed ML20209H4431999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for May 1999 on Unit Shutdowns Also Encl ML20210A5771999-07-14014 July 1999 Forwards Revsied Catawba Nuclear Station Selected Licensee Commitments Manual, Per 10CFR50.71(e),changing Sections 16.7-5,16.8-5,16.9-1,16.9-3,16.9-5 & 16.11-7.Manual Constitute Chapter 16 of UFSAR ML20216D3941999-07-14014 July 1999 Forwards Revs to Catawba Nuclear Station Selected Licensee Commitments Manual NUREG-1431, Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation1999-07-0909 July 1999 Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196L0371999-07-0808 July 1999 Approves Requested Schedule Change of Current two-year Requalification Examinations to non-outage dates.Two-year Cycle Will Start on 991001 & Will End on 020930 05000413/LER-1999-008, Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach1999-07-0808 July 1999 Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach ML20196J9001999-07-0606 July 1999 Informs That 990520 Submittal of Rept DPC-NE-3004-PA,Rev 1, Mass & Energy Release & Containment Response Methodology, Marked Proprietary Will Be Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 IR 05000413/19990031999-07-0101 July 1999 Discusses Insp Repts 50-413/99-03 & 50-414/99-03 Completed on 990605 & Transmitted by Ltr .Results of Delibrations for Violation Re Discovery of Potentially More Limiting Single Failure Affecting SGTS Analysis Provided 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217H0041999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217F1301999-10-0707 October 1999 Forwards Rev 1 to Request for Relief 99-03 from Requirements of ASME B&PV Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting (Vg) Sys 05000414/LER-1999-004, Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments1999-09-27027 September 1999 Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments 05000413/LER-1999-015, Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept1999-09-27027 September 1999 Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept 05000414/LER-1999-005, Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments1999-09-20020 September 1999 Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments ML20212D5321999-09-15015 September 1999 Informs That Duke Energy Corp Agrees to Restrict Max Fuel Rod Average Burnup to 60,000 Mwd/Mtu,In Order to Support NRC Final Approval & Issuance of Requested Amend ML20212B4641999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for Catawba Nuclear Station,Units 1 & 2 ML20212A5191999-09-0808 September 1999 Requests NRC Approval for Relief from Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,App VI,VI-2430(c) & 2440(b).Approval of 99-GO-002 Is Requested by 000301 05000413/LER-1999-014, Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment1999-09-0101 September 1999 Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment 05000414/LER-1999-003, Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev1999-08-31031 August 1999 Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev 0 of LER ML20211H1741999-08-30030 August 1999 Forwards Comments on Catawba Nuclear Station Units 1 & 2 & McGuire Nuclear Station,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid.Ltr Dtd 990107,rept ATI-98-012-T005 & Partial marked-up Rept WCAP-14995 Encl ML20211M4451999-08-30030 August 1999 Forwards Summary of Util Conclusions Re Outstanding Compliance Issue Re Staff Interpretation of TS SR 3.0.1,per Insp Repts 50-369/99-03 & 50-370/99-03,as Discussed with NRC During 990618 Meeting 05000413/LER-1999-013, Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER1999-08-25025 August 1999 Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER ML20211B9471999-08-18018 August 1999 Forwards Request for Relief 99-02,associated with Limited Exam Results for Welds Which Were Inspected During Unit 1 End of Cycle 11 RFO ML20211C1191999-08-18018 August 1999 Forwards ISI Rept Unit 1 Catawba 1999 RFO 11, Providing Results of ISI Effort Associated with End of Cycle 11 ML20211C3651999-08-17017 August 1999 Forwards Rev 25 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program, Which Includes Reformatting of Manual & Addl Changes as Noted in Attached Summary of Changes ML20211F2971999-08-17017 August 1999 Forwards non-proprietary & Proprietary Updated Pages for DPC-NE-2009,submitted 980722.Pages Modify Fuel Design & thermal-hydraulic Analysis Sections of DPC-NE-2009. Proprietary Page 2-4 Withheld,Per 10CFR2.790 05000413/LER-1999-011, Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment1999-08-16016 August 1999 Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment ML20211B1121999-08-16016 August 1999 Forwards Topical Rept DPC-NE-2012, Dynamic Rod Worth Measurement Using Casmo/Simulate, Describing Results of Six Drwm Benchmark Cycles at Catawba & McGuire & Discusses Qualification to Use Drwm at Catawba & McGuire ML20210S2751999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl ML20210N9521999-08-0404 August 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual.Documents Constitutes Chapter 16 of Ufsar.With List of Effective Pages ML20210M6411999-07-29029 July 1999 Forwards Request for Relief 99-03 from Requirements of ASME Boiler & Pressure Vessel Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting Air (Vg) Sys 05000413/LER-1999-010, Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units1999-07-22022 July 1999 Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units 05000413/LER-1999-009, Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept1999-07-19019 July 1999 Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept 05000414/LER-1999-001, Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed1999-07-15015 July 1999 Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed ML20216D3941999-07-14014 July 1999 Forwards Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20209H4431999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for May 1999 on Unit Shutdowns Also Encl ML20210A5771999-07-14014 July 1999 Forwards Revsied Catawba Nuclear Station Selected Licensee Commitments Manual, Per 10CFR50.71(e),changing Sections 16.7-5,16.8-5,16.9-1,16.9-3,16.9-5 & 16.11-7.Manual Constitute Chapter 16 of UFSAR 05000413/LER-1999-008, Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach1999-07-0808 July 1999 Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach ML20196G7461999-06-22022 June 1999 Requests Exemption from Requirements of 10CFR54.17(c) That Application for Renewed Operating License Not Be Submitted to NRC Earlier than 20 Yrs Before Expiration of Operating License Currently in Effect ML20196E9541999-06-18018 June 1999 Forwards SG Tube Insp Conducted During Unit 1 End of Cycle 11 Refueling Outage.Attachments 1,2,3 & 4 Identify Tubes with Imperfections in SGs A,B,C & D,Respectively ML20195K4571999-06-14014 June 1999 Forwards MORs for May 1999 & Revised MORs for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20195J1691999-06-10010 June 1999 Forwards Written Documentation of Background & Technical Info Supporting Catawba Unit 1,notice of Enforcement Discretion Request Re TS 3.5.2 (ECCS-Operating),TS 3.7.12 (Auxiliary Bldg Filtered Ventilation Exhaust Sys) ML20217G5771999-06-0909 June 1999 Forwards Post Exam Comments & Supporting Reference Matls for Written Exams Administered at Catawba Nuclear Station on 990603 05000414/LER-1999-002, Forwards Abstract of LER 99-002-00 Re Forced Shutdown of Plant as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Final LER Will Be Submitted No Later than 9907081999-06-0303 June 1999 Forwards Abstract of LER 99-002-00 Re Forced Shutdown of Plant as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Final LER Will Be Submitted No Later than 990708 ML20207F2381999-06-0101 June 1999 Forwards Copy of Catawba Nuclear Station Units 1 & 2 1998 10CFR50.59 Rept, for NRC Files ML20195J1131999-05-26026 May 1999 Requests Approval to Change Cycle Dates for Two Year Requalification Training Program Required by 10CFR55.59,to Improve Scheduling of Requalification Exams to non-outage Periods 05000413/LER-1999-007, Forwards LER 99-007-00,re Operation Prohibited by TS 3.4.7. Commitments Identified in LER Are Listed in Planned Corrective Actions Section1999-05-26026 May 1999 Forwards LER 99-007-00,re Operation Prohibited by TS 3.4.7. Commitments Identified in LER Are Listed in Planned Corrective Actions Section ML20195B4751999-05-24024 May 1999 Forwards Rev 7 to UFSAR Chapter 2 & Chapter 3 from 1998 UFSAR for Catawba Nuclear Station.List of Instructions on Insertion Encl ML20196L1851999-05-20020 May 1999 Forwards Proprietary & non-proprietary Version of Rev 1 to TR DPC-NE-3004, Mass & Energy Release & Containment Response Methodology, Consisting of Finer Nodalization of Ice Condenser Region.Proprietary Info Withheld ML20196L1791999-05-20020 May 1999 Communicates Util Licensing Position Re Inoperable Snubbers. Licensee Has Determined That Structure of ITS Has Resulted in Certain Confusion Re Treatment of Inoperable Snubbers 05000413/LER-1997-009, Forwards LER 97-009-02, Unanalyzed Postulated Single Failure Affecting SG Tube Rupture Analysis, Suppl Revises Planned C/A Described in Suppl 1 to Ler.Current Status of C/As & Addl C/As Planned,Provided in Rept1999-05-17017 May 1999 Forwards LER 97-009-02, Unanalyzed Postulated Single Failure Affecting SG Tube Rupture Analysis, Suppl Revises Planned C/A Described in Suppl 1 to Ler.Current Status of C/As & Addl C/As Planned,Provided in Rept ML20206T4481999-05-13013 May 1999 Forwards Rev 3 to Topical Rept DPC-NE-3002-A, UFSAR Chapter 15 Sys Transient Analysis Methodology, IAW Guidance Contained in NUREG-0390 ML20206R1721999-05-13013 May 1999 Forwards Monthly Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 & Revised Monthly Operating Repts for Mar 1999 ML20206T0281999-05-12012 May 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual. Document Constitutes Chapter 16 of UFSAR 05000413/LER-1999-006, Forwards LER 99-006-00,re CR Ventilation Sys Inoperability. Root Cause & Corrective Actions for Occurence Are Being Finalized & Will Be Reported in Supplement Rept on 9906071999-05-10010 May 1999 Forwards LER 99-006-00,re CR Ventilation Sys Inoperability. Root Cause & Corrective Actions for Occurence Are Being Finalized & Will Be Reported in Supplement Rept on 990607 ML20206N8201999-05-10010 May 1999 Forwards Revs 15 & 16 to Catawba Unit 1 Cycle 12 COLR, Per TS 5.6.5.Rev 15 Updates Limits for New Catawba 1 Cycle 12 Reload Core & Rev 16 Revises Values Re Min Boron Concentrations for Rwst,Cla & SFP ML20206J4431999-05-0303 May 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual, Per 10CFR50.71(e).Document Constitutes Chapter 16 of UFSAR ML20206D2141999-04-29029 April 1999 Forwards 1998 Annual Radioactive Effluent Release Rept for Catawba Nuclear Station,Units 1 & 2, Per Plant TS 5.6.3. Rept Contains Listed Documents ML20206E4101999-04-26026 April 1999 Forwards Four Copies of Rev 9 Todpc Nuclear Security & Contingency Plan,Per 10CFR50.54(p)(2).Changes Do Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 1999-09-08
[Table view] |
Text
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1 ..
11 1 Duke n>urr Compan, PH31831 M Catawba Training Center 400 Concord Road
%rk, SC 2976 DUKEPOWER July 14, 1992
'IO: Neal K. Hunemutiler Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Oxanission Washington, D.C. 20555 I W 14: Jon D. Wylie Manager, Catawba Trainity SUBJDCr: Sinulator Four 'ic- Pecort
'Ihis report is subnitto:1 as the four year report for the Catawba Nuclear Station Unit One Sinulator in accordance with 10CFR50.45 b.5.ii and b.5.vi.
The required information is included in the form of attachments to this letter as follows:
ATIAct m E 1.0 FAILED TEST IPOCEIJURES ATTAONU 2.0 DESCRIFfl0N OF TESfS O24PIRITD (1988-1991)
ATIAOME 3.0 NEXf FOUR YEAR TEST SCHEDULE (1992-1995)
If tlw.re are any questions concernirg this report, please feel free to call or write:-
Glenn Spurlin Director, Tech Services Trrg Catawba Nuclear Station 4850 Canoord Road -
York, S.C. 29745 Phone 803-831-3117
'Ihank you for your attention in this matter.
J.D.*'Wyliev cc: R.C.'Futrell M.S. Tuckman W.R. McCollum-6 U *i U ()
h 9207030082 920714 sk PDR ADOCK 05000413 -
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. r ATTAONDfP 1 FAIIlD TEST PROCEDURES There are no test failures perdiry. All failed tests have been corrected and retested satisfactorily. Nine tests have had work requests written to correct problem. All work requests are ocanplete and satisfactory. A list of these tests and completed work requests follows.
1988 Malfunction EPL2 hR / AFWOO7 Problem existad with Aux Iocs of Vital Bus Feedwater valve indications.
1989 Steady State Test WR / CFWO15 Feed header and feed pump parameters were inconsistent with plant data.
HR / RCP003 Reactor Coolant Pump bry temps were inconsistent with plant data.
1989 loss of Feedwater WR / O E005 Obtained data for sump With an ATWS temperature and other containment parameters.
1989 Small Break IOCA WR / ON005 Same as above.
With ICC.
WR / ON006 Obtained data for Containment M.
1990 Malfunction IRX13 hR # PCS012 Insufficient options on bank Improper Overlap overlap failure selections.
1990 Malfunction VIX1 KR / CFWO24 Feed pump suction pressure loss of VI meters had %Torg power supply.
1990 Malfunction EPX8 hR / DSG001 D/G kulld not trip as per the Ioss of 4160 Bus malfunction description.
1991 Malfunction EPIA hR / EPS007 Various wronry power supolies.
Ioss of Protective system Bus.
-1991 Malfunction MrX3 h2 / CFWO30 Loss of cordenser vacuum did Loss of Condenser not occur as expected.
Vacuum.
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L Description of Tests Otxtpleted - 1988 Attachment 2 Translents Otzmletion QatJ Transient #1 - S/G Tube Inak 11/28/88 Transient #2 -
Iartje Break IOCA 12/12/88 Transient #3 -
Small Break IOCA 12/06/88 Transient #4 -
loss of Offsite Poer 12/13/88 Transient #5 -
Single NC Pump Trip 11/14/88 Transient #6 -
Ioss of Main Foodsater 11/22/68 Transient #7 -
Ircs of All Feedsater 11/29/88 Transient #8 - Dropped Rod (EOL and BOL) 11/22/88 Transient #9 -
Ioad Rejection 11/28/88 Transient #10 - Spray Valve Failure 10/14/88 Transient #11 - Reactor Trip 12/28/88 Transient #12 - Steant Line Break 10/18/88 Transient #13 - Feedwater Line Break 11/28/88 Transient #14 - Incs of CF NIWS 11/28/88 Transient #15 - Small Break LCK.A ICC 11/28/88 Transient #16 - S/G Tube Rupture w/SM PORV Fail 10/07/88 Malfunctions Ctroletion Date NDX4 -
ND Punp Discharge Rupture 12/08/88 EPL2 -
Ioss of Vital Qumnel 12/06/88 KCX2 -
KC Relief Valve Failure 12/27/88 ~
IRX10 - Stuck Rod 11/01/88 ODC1 -
Variable NC Activity 11/28/88 EB2 -
Main Generator Breaker Trip 17./28/88 ILE1 -
PZR Level Master Failure 11/29/88 NCX2 -
PZR PORV Failure 11/17/88 CFX7 -
r!ain Feedline Break 11/29/88 Others Completion Date Steady State / Normal Ops Test 12/14/88 (Four Pomr levels, including the one hour at 100% normal operations)
Sin 11ator Real Time Test 01/06/89 I
Description of 'Ibsts Ctupleted - 1989 Attadunent 2 Transients Oroletion Date Transient #1 -
S/G Tube Imk 10/25/89 Transient #2 -
Iarge 3reak IOCA 03/06/89 Transient #3 -
Small Break IOCA 05/24/89 Trancient #4 -
Ioss of Offaite Pcuer 11/02/89 Transient #5 -
Single NC PLmp Trip 03/06/89 Transient #6 - Ioss of Main Feedwater 05/25/89 Transient #7 -
Ioss of All Feedwater 11/03/89 Transient #8 -
Droppod Rod (EOL and BOL) 04/11/89 Transient #' -
Icad Re-lection 05/22/89 Transient #10 - Spray Valve Failure G5/15/89 Transient #11 - Reacter Trip 05/22/89 Transient #12 - Steam Line Break 05/25/89 Transient #13 - Fe(denter Line Break 04/20/89 Transient #14 - Ioss of CF A'IMS 11/03/89 Transient #15 - ! ball Break IDCA ICC 11/03/89 Transient #16 - ,/G 'Ibbe Rupture w/SM IWv' Fail 03/14/89 Malfunctions Opmplglign Date SGX1 -
NIR 01/30/89 NCX7 -
NC Imk 04/25/89 EPX2 -
Ioss of Switchyard 03/06/89 "
DGX1 -
D/G Failure to Start 05/22/89 RfDO -
BN Pump Failure 05/23/89 CFX1 -
Ioss of IMPT Vacuum 05/25/89 IRX6 -
Drcpped Rod 11/02/89 IRX9 -
Rods Fail to Move 05/25/89 IRX3 -
Uncontrolled Rod Motion 05/25/89 SMX7 - Steam Line Break Inside Containment 11/06/89 Others Camoletion Date Steady State / Normal Ops Test 11/02/89 (Four Power levels, includity the one hour at 100% normal operations)
Simulator Real Time Test 11/02/89
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Description of ibst OTpletal - 1990 Attachment 2 Transients Cnoletion M Transient #1 -
S/G 7\1bo Irak 03/29/90 Transient #2 -
Large Break LOC'A 04/18/90 Transient #3 -
Small Break IDCA 04/18/90 Transient #4 -
Loss of Offsite Poer 07/03/90 Transient #5 -
Single NC Pump Trip 04/11/90 Transient #6 -
Ioss of Main Foodwater 04/18/90 Transient #7 -
Ioss of All Feal*'ater 03/29/90 4 Transient #6 -
Dropped Rod (IDL and DOL) 04/24/90 Transient #9 -
Load Rejection 04/24/90 Transient #10 - Spray Valve Failure 04/24/90 Transient #11 - Reactor Trip 03/27/90 Transient #12 - Steam Line Break 04/18/90 Transient #13 - Featvater Line Break 03/29/90 Transient #14 - I.cca of CF ATWS 03/30/90 Transient #15 - Small Break IOCA ICC 06/01/90 Transient #16 - S/G Tube @ tre w/SM PORV Fail 04/18/90 Malfunctions Comoletign Date NCXd -
IDCA 05/30/90 VIX1 -
Loss of VI 05/15/90 EPX8 -
Loss of 4160 VAC Bus 06/20/90 (
NCP1 -
NCP Trip 04/26/90 IRX13 - Iuprcper Overlap 05/07/90 HIC 1 - Inadvertent Turbine Trip 05/30/90 DiB11 - Power Range Det. Failure 04/26/90 IPE1 -
PZR Master Pressum Controller Failure 06/11/90 IPX1 -
Auto Reactor Trip Failure 06/11/90 Others Ctroletion Date Steady State / Normal Ops Test 01/02/91 (Four Pter levels, including the one hour at 100% normal operations)
Sin 11ator Real Time Test 12/28/90 1
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J Description of Tests ccmpleta:1 - 1991 Attachment- 2 Traraig h letion Data Transient #1 -
S/G 'Ibbe Isak 09/10/91 Transient #2 -
Large Break IDCA 09/10/91 Transient #3 -
Small Break IDCA 09/10/91 Transient-(4 -
Ioss of Offsite Power 12/30/91 Transient #5 - Single NC Punp Trip 11/06/91
= Trannient #6 -- Ioss of Main Feedwater 11/18/91
!.c Transient #7 -
Ioss of All Feedwater 12/09/91 Transient #8. : :Ikuwad Rod (EDL and BOL) 11/04/91 Transient #9 -
Ioad Rejection 12/16/91 Transient #10 - Spray Valve Failure 11/06/91 Transient #111- Reactor Trip 11/15/91 Transient #12 - Steam Line Break 11/06/91 Transient #13 - Feedwater Line Break 11/11/91 Transient #14 - Ioss of CF A'IWS 11/11/91 Transient #15 - Small Break LOCA ICC 12/11/91 Transier2 #16 - S/G Tube Rupture w/SM ICRV Fall 11/18/91 Malfunctions .CQrtoletion Date NCX3 -- -PZR Safety Failure 09/10/91 EPX5 -
Ioss of.6900 Switchgear 09/10/91 MIX 3 .--- Ioss of-Cond, Vacuum 09/10/91 NDX1 ND Punp Failure; 11/25/91 MLT2 - Ioss of All Feedwater 09/10/91 EPL4' -
Ioss 'of Protective System Channel 12/30/91 IRE 1 -
PImaca Instrument and Cbntrol Failure 11/18/91 NIX 4 -
ECX:S Header Vlvs Fail to Open on EOCS 11/25/91 IRX2 -
Uncontrolled Rod Withdrawal 11/18/91 Others Ccroletion Date Steady State /Norinal Ops Test 12/16/91 (Four Power levels, including the one inIr at 100%. normal operations) .j Sinulator Real Time 'Ibst 11/11/91 d
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Attactment 3 - Four Year Test Schedule Amual- Simulator %stirq Schedule fcr 2292 Transients:
Transient #1 - S/G' Tube Isak Transient'#2 -: Iarge Break INA
-Transient #3 -
Small Break INA Transient #4 -
Ioss of offsite' Power Transient #5 -
Sirgle NC Puup Trip
- i. Transient #6 - Ioss of Main Feedwater-Transient #7 - Ioss of All'7%edwater Transient #8 -
Drcpped Ibd- (EDL and IKL)
Transient #9 - Imad Rejection Transient #10 - Spray Valve' Failure Transient #11~- Reactor Trip j; Transient #12 - Steam Line Break Transient #13 - Feaowater Line Break Transient #14 - Imas of CF AINS Transient #15 '
Small Break ITA IOC Transient #16 - S/G Tube Rupture with SM PORV Failure
_ Malfunctions:
lI NDX4~ - ND Punp Discharge Rupture EPI 2. - Ioss of Vir.al Channel l3 KCX2 - KC Relief Valve Failure l
IRX10 - Stuck Rod ODCl- -
Variable NC Activity l EGB2 -
~ Main Generator Breaker Trip' ILEl - PZR Invel Master Failure-NCX2 -
PZR TORV Failure CFX7 -
Main Feedline Break L
others:
Steady State / Normal Ops Test - (Four Power levels, includirg the one hour at ;
100% normal operations)
Sirallator Real Time Test 4
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Attachment 3 - Four Year Test Schedule Annual simulator 'msting Schedule for 1923 Transients:
Transient #1 -
S/G Tube Inak Transient #2 -
Iarge Break IOCA Transient /3 -
Str9 Break IDCA Transient #4 -
Ioss of Offsite Power Transient #5 -
Single NC Punp Trip Transient #6 -
Icss of Main Foodwater Transient #7 -
loss of All Foodwater Transient #8 -
Drcppcd Rod (IDL ard BOL)
Transient #9 -
Ioad Rejection Transient #10 - Spray Valve Failure Transient #11 - Reactor Trip Transient #12 - Steam Line Break Transient #13 - Feedwater Line Break Transjent #14 - Loss of CF ATWS Transient #15 - Small Break IDCA ICC Transient #16 - S/G Tube Rupture with SM PORY Failure Malfunctions:
SGX1 -
SGIR NCX7 -
NC Isak EPX2 -
Icss of Switch)wd DGX1 -
D/G Failure to Scart RNX3 -
RN Pump Failure CFX1 -
Ioss of EWPT Vacuum IRX6 -
Dropped Rod IRX9 - Rods Fail to Move IRX3 -
Uncontrolled Rod Motion SMX7 '- Steam Line Break Inside Containment Others:
Steady State / Normal Ops Test - (Four Power levels, including the one hour at 100% normal operations)
Sinulator Real Time Test
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Attachment 3 - Four Year ' list Scfwtif e
. Anrual Slim 11ator Testing Sctadale for lati Transients:
Transient #1 - S/G Tobe Imak Transient #2 -
targe Break ICCA Transient #3~ - Small- Break IDCA Transient #4 '- Ioss of Offsite Power Transient #5 - Single NC Pug Trip
. Transient #6 -
Ima of Main' Feedwater Transient #7- -
Ioss of All Feedw '.er Transient #8 - .Ikgyed Rod (EDL M BOL)
Transient #9 -
Load _ Rejection Transient #10 - Spray-Valve Failure TrerAf ont #11 - Reactor Trip- '
h rnh st #12 -' Steam ~Line Break Transient #13 - Feedwater Line Break Transient #14 -- Ioss of CF A'IWS Transient #15 - Small Break IOCA ICC Transient #16 - S/G Tube Rupture with SM PORV Failure
, Malfunctions:
NCX8 - IDCA VIX1 ~ Ims of VI EPX8 -
Ioss of.4160 VAC Bus NCP1 - NCP Trip IRX13 - Igroper. Overlap DiC1 -
Inadvertent Turbine Trip ENB11 - Power Range Det. Failure IPE1 - PZR Master Pressure Controller Failure IPX1- -
Auto Reactor Trip Failure
- - - Others
Steady State / Normal Ops Test - (Four Power levels, includirg the one hour at ~
100% normal operations)
Shulator Real Time Test
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-i Attachment Four Year Test Sdwhile Anrmal Simulatcr Testing ScMile for 1225 Transients: ,
f Transient #1 -
S/G Tube Imak Transient #2 -
Iarge Break IOCA Transient #3 -
Small Break IDCA Transient #4 - Ioss of.Offaite Power 4 - Transient #5; - Single NC Punp Trip Transient #6.-- loss of Edn Feedwater Transient #7 --- Ioss of All Feedwater Transient #8 -
Dropped Rod (EDL and BOL)
Transient #9 -
Inad Rejection-Transient #10 - Spray Valve Failure Transient #11 - Reactor Trip Transient #12 - Steam Idne Break Transient #13 - --Feedwater Line Break Transient #14 - Ioss of CF'A7WS Transient #15'- Small Break IOCA 100 Transient #16 -- S/G 'Ibbe Ruptun with SM PORV Failure '
Malfunctions:
NCX3 - PZR Safety Failure EPX5 '- Ioss of 6900 SwitdxJear
- MrX3 - Ioss of Cond. Vacuum ND Puup Failure
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NDX1: -
MLT2 - siam of All Feedwater EPL4 :- Ioss of Protective System Channel IRE 1 -
Pr - Instrument and Control Failure NIX 4 -
ECCS Fmelar Valves Fail.to..Open on ECCS Activation
'IRX2 -
Uncontrolled Rod Withdrawal others:-
Steady State / Normal Ops Test - (Four Power levels, including the one hour at 100% normal operations)
Sinulator Real Time Test
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