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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F8231999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of Catawba Nuclear Station.Based on Review,Nrc Did Not Identify Any New Areas That Warranted More than Core Insp Program Over Next Five Months.Historical Listing of Issues,Encl ML20217H0041999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217F1301999-10-0707 October 1999 Forwards Rev 1 to Request for Relief 99-03 from Requirements of ASME B&PV Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting (Vg) Sys ML20212J3011999-10-0101 October 1999 Forwards Exemption from Certain Requirements of 10CFR54.17(c) Re Schedule for Submitting Application for Operating License Renewal.Se Also Encl ML20217K2651999-10-0101 October 1999 Forwards Retake Exams Repts 50-413/99-302 & 50-414/99-302 on 990921-23.Two of Three ROs & One SRO Who Received Administrative Section of Exam Passed Retake Exam, Representing 75 Percent Pass Rate 05000414/LER-1999-004, Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments1999-09-27027 September 1999 Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments 05000413/LER-1999-015, Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept1999-09-27027 September 1999 Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept ML20217A7911999-09-24024 September 1999 Forwards Insp Repts 50-413/99-05 & 50-414/99-05 on 990718- 0828 at Catawba Facility.Nine NCVs Identified Involving Inadequate Corrective Actions Associated with Degraded Svc Water Supply Piping to Auxiliary Feedwater Sys ML20212E6471999-09-24024 September 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for Catawba NPP & 990615.Informs That NRC Reviewed Response for Catawba & Concluded That All Requested Info Provided.Considers GL 98-01 to Be Closed for Catawba ML20212F0941999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals for Cns,Units 1 & 2 ML20212M2001999-09-20020 September 1999 Confirms 990913 Telcon Between M Purser & R Carroll Re Management Meeting to Be Conducted on 991026 in Atlanta,Ga to Discuss Operator Licensing Issues 05000414/LER-1999-005, Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments1999-09-20020 September 1999 Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments ML20212D5321999-09-15015 September 1999 Informs That Duke Energy Corp Agrees to Restrict Max Fuel Rod Average Burnup to 60,000 Mwd/Mtu,In Order to Support NRC Final Approval & Issuance of Requested Amend ML20212B4641999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for Catawba Nuclear Station,Units 1 & 2 ML20212A4131999-09-14014 September 1999 Informs That TR DPC-NE-2009P Submitted in 990817 Affidavit, Marked Proprietary,Will Be Withheld from Public Disclosure, Pursuant to 10CFR2.709(b) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20212M1931999-09-13013 September 1999 Refers to 990909 Meeting Conducted at Region II Office Re Presentation of Licensee self-assessment of Catawba Nuclear Station Performance.List of Attendees & Licensee Presentation Handout Encl ML20212A3751999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementation Code Case for Duration of Insp Interval ML20212A5191999-09-0808 September 1999 Requests NRC Approval for Relief from Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,App VI,VI-2430(c) & 2440(b).Approval of 99-GO-002 Is Requested by 000301 05000413/LER-1999-014, Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment1999-09-0101 September 1999 Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment 05000414/LER-1999-003, Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev1999-08-31031 August 1999 Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev 0 of LER ML20211H1741999-08-30030 August 1999 Forwards Comments on Catawba Nuclear Station Units 1 & 2 & McGuire Nuclear Station,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid.Ltr Dtd 990107,rept ATI-98-012-T005 & Partial marked-up Rept WCAP-14995 Encl ML20211M4451999-08-30030 August 1999 Forwards Summary of Util Conclusions Re Outstanding Compliance Issue Re Staff Interpretation of TS SR 3.0.1,per Insp Repts 50-369/99-03 & 50-370/99-03,as Discussed with NRC During 990618 Meeting 05000413/LER-1999-013, Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER1999-08-25025 August 1999 Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER ML20211M8191999-08-25025 August 1999 Confirms 990825 Telcon Between G Gilbert & R Carroll Re Mgt Meeting to Be Held on 990909 in Atlanta,Ga,To Allow Licensee to Present self-assessment of Catawba Nuclear Station Performance ML20211A9641999-08-20020 August 1999 Forwards SE Authorizing Licensee 990118 Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section XI for Plant,Units 2 ML20211C1191999-08-18018 August 1999 Forwards ISI Rept Unit 1 Catawba 1999 RFO 11, Providing Results of ISI Effort Associated with End of Cycle 11 ML20211B9471999-08-18018 August 1999 Forwards Request for Relief 99-02,associated with Limited Exam Results for Welds Which Were Inspected During Unit 1 End of Cycle 11 RFO ML20211C3651999-08-17017 August 1999 Forwards Rev 25 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program, Which Includes Reformatting of Manual & Addl Changes as Noted in Attached Summary of Changes ML20211F2971999-08-17017 August 1999 Forwards non-proprietary & Proprietary Updated Pages for DPC-NE-2009,submitted 980722.Pages Modify Fuel Design & thermal-hydraulic Analysis Sections of DPC-NE-2009. Proprietary Page 2-4 Withheld,Per 10CFR2.790 05000413/LER-1999-011, Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment1999-08-16016 August 1999 Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment ML20211B1121999-08-16016 August 1999 Forwards Topical Rept DPC-NE-2012, Dynamic Rod Worth Measurement Using Casmo/Simulate, Describing Results of Six Drwm Benchmark Cycles at Catawba & McGuire & Discusses Qualification to Use Drwm at Catawba & McGuire ML20210V0321999-08-13013 August 1999 Forwards Insp Repts 50-413/99-04 & 50-414/99-04 on 990606- 0717.Six Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20210S2751999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl ML20210Q3751999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr as Listed,Thirty Days Before Exam Date,In Order to Register Individuals for Exam ML20210N9521999-08-0404 August 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual.Documents Constitutes Chapter 16 of Ufsar.With List of Effective Pages IR 05000413/19980131999-08-0202 August 1999 Discusses Integrated Insp Repts 50-413/98-13,50-414/98-13, 50-413/98-16,50-414/98-16 & NRC Special Repts 50/413/99-11 & 50-414/99-11 Conducted Between Aug 1998 & May 1999.Six Violations Occurred,Based on OI Investigation & Insp ML20210M6411999-07-29029 July 1999 Forwards Request for Relief 99-03 from Requirements of ASME Boiler & Pressure Vessel Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting Air (Vg) Sys 05000413/LER-1999-010, Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units1999-07-22022 July 1999 Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units IR 05000413/19990101999-07-22022 July 1999 Discusses Insp Rept 50-413/99-10 & 50-414/99-10 on 990314- 0424 & Forwards Notice of Violation Re Failure to Comply with TS 3.7.13,when Misalignment of Two Electrical Breakers Rendered SSS Inoperable from 981216-29 ML20217G5241999-07-20020 July 1999 Forwards Exam Repts 50-413/99-301 & 50-414/99-301 on 990524- 27,0603,07-10 & 16.Of Fourteen SRO & RO Applicants Who Received Written Exams & Operating Tests,Eight Applicants Passed & Six Failed Exam 05000413/LER-1999-009, Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept1999-07-19019 July 1999 Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept 05000414/LER-1999-001, Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed1999-07-15015 July 1999 Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed ML20209H4431999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for May 1999 on Unit Shutdowns Also Encl ML20210A5771999-07-14014 July 1999 Forwards Revsied Catawba Nuclear Station Selected Licensee Commitments Manual, Per 10CFR50.71(e),changing Sections 16.7-5,16.8-5,16.9-1,16.9-3,16.9-5 & 16.11-7.Manual Constitute Chapter 16 of UFSAR ML20216D3941999-07-14014 July 1999 Forwards Revs to Catawba Nuclear Station Selected Licensee Commitments Manual NUREG-1431, Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation1999-07-0909 July 1999 Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196L0371999-07-0808 July 1999 Approves Requested Schedule Change of Current two-year Requalification Examinations to non-outage dates.Two-year Cycle Will Start on 991001 & Will End on 020930 05000413/LER-1999-008, Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach1999-07-0808 July 1999 Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach ML20196J9001999-07-0606 July 1999 Informs That 990520 Submittal of Rept DPC-NE-3004-PA,Rev 1, Mass & Energy Release & Containment Response Methodology, Marked Proprietary Will Be Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 IR 05000413/19990031999-07-0101 July 1999 Discusses Insp Repts 50-413/99-03 & 50-414/99-03 Completed on 990605 & Transmitted by Ltr .Results of Delibrations for Violation Re Discovery of Potentially More Limiting Single Failure Affecting SGTS Analysis Provided 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217H0041999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217F1301999-10-0707 October 1999 Forwards Rev 1 to Request for Relief 99-03 from Requirements of ASME B&PV Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting (Vg) Sys 05000414/LER-1999-004, Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments1999-09-27027 September 1999 Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments 05000413/LER-1999-015, Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept1999-09-27027 September 1999 Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept 05000414/LER-1999-005, Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments1999-09-20020 September 1999 Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments ML20212D5321999-09-15015 September 1999 Informs That Duke Energy Corp Agrees to Restrict Max Fuel Rod Average Burnup to 60,000 Mwd/Mtu,In Order to Support NRC Final Approval & Issuance of Requested Amend ML20212B4641999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for Catawba Nuclear Station,Units 1 & 2 ML20212A5191999-09-0808 September 1999 Requests NRC Approval for Relief from Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,App VI,VI-2430(c) & 2440(b).Approval of 99-GO-002 Is Requested by 000301 05000413/LER-1999-014, Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment1999-09-0101 September 1999 Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment 05000414/LER-1999-003, Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev1999-08-31031 August 1999 Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev 0 of LER ML20211H1741999-08-30030 August 1999 Forwards Comments on Catawba Nuclear Station Units 1 & 2 & McGuire Nuclear Station,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid.Ltr Dtd 990107,rept ATI-98-012-T005 & Partial marked-up Rept WCAP-14995 Encl ML20211M4451999-08-30030 August 1999 Forwards Summary of Util Conclusions Re Outstanding Compliance Issue Re Staff Interpretation of TS SR 3.0.1,per Insp Repts 50-369/99-03 & 50-370/99-03,as Discussed with NRC During 990618 Meeting 05000413/LER-1999-013, Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER1999-08-25025 August 1999 Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER ML20211B9471999-08-18018 August 1999 Forwards Request for Relief 99-02,associated with Limited Exam Results for Welds Which Were Inspected During Unit 1 End of Cycle 11 RFO ML20211C1191999-08-18018 August 1999 Forwards ISI Rept Unit 1 Catawba 1999 RFO 11, Providing Results of ISI Effort Associated with End of Cycle 11 ML20211C3651999-08-17017 August 1999 Forwards Rev 25 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program, Which Includes Reformatting of Manual & Addl Changes as Noted in Attached Summary of Changes ML20211F2971999-08-17017 August 1999 Forwards non-proprietary & Proprietary Updated Pages for DPC-NE-2009,submitted 980722.Pages Modify Fuel Design & thermal-hydraulic Analysis Sections of DPC-NE-2009. Proprietary Page 2-4 Withheld,Per 10CFR2.790 05000413/LER-1999-011, Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment1999-08-16016 August 1999 Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment ML20211B1121999-08-16016 August 1999 Forwards Topical Rept DPC-NE-2012, Dynamic Rod Worth Measurement Using Casmo/Simulate, Describing Results of Six Drwm Benchmark Cycles at Catawba & McGuire & Discusses Qualification to Use Drwm at Catawba & McGuire ML20210S2751999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl ML20210N9521999-08-0404 August 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual.Documents Constitutes Chapter 16 of Ufsar.With List of Effective Pages ML20210M6411999-07-29029 July 1999 Forwards Request for Relief 99-03 from Requirements of ASME Boiler & Pressure Vessel Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting Air (Vg) Sys 05000413/LER-1999-010, Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units1999-07-22022 July 1999 Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units 05000413/LER-1999-009, Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept1999-07-19019 July 1999 Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept 05000414/LER-1999-001, Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed1999-07-15015 July 1999 Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed ML20216D3941999-07-14014 July 1999 Forwards Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20209H4431999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for May 1999 on Unit Shutdowns Also Encl ML20210A5771999-07-14014 July 1999 Forwards Revsied Catawba Nuclear Station Selected Licensee Commitments Manual, Per 10CFR50.71(e),changing Sections 16.7-5,16.8-5,16.9-1,16.9-3,16.9-5 & 16.11-7.Manual Constitute Chapter 16 of UFSAR 05000413/LER-1999-008, Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach1999-07-0808 July 1999 Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach ML20196G7461999-06-22022 June 1999 Requests Exemption from Requirements of 10CFR54.17(c) That Application for Renewed Operating License Not Be Submitted to NRC Earlier than 20 Yrs Before Expiration of Operating License Currently in Effect ML20196E9541999-06-18018 June 1999 Forwards SG Tube Insp Conducted During Unit 1 End of Cycle 11 Refueling Outage.Attachments 1,2,3 & 4 Identify Tubes with Imperfections in SGs A,B,C & D,Respectively ML20195K4571999-06-14014 June 1999 Forwards MORs for May 1999 & Revised MORs for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20195J1691999-06-10010 June 1999 Forwards Written Documentation of Background & Technical Info Supporting Catawba Unit 1,notice of Enforcement Discretion Request Re TS 3.5.2 (ECCS-Operating),TS 3.7.12 (Auxiliary Bldg Filtered Ventilation Exhaust Sys) ML20217G5771999-06-0909 June 1999 Forwards Post Exam Comments & Supporting Reference Matls for Written Exams Administered at Catawba Nuclear Station on 990603 05000414/LER-1999-002, Forwards Abstract of LER 99-002-00 Re Forced Shutdown of Plant as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Final LER Will Be Submitted No Later than 9907081999-06-0303 June 1999 Forwards Abstract of LER 99-002-00 Re Forced Shutdown of Plant as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Final LER Will Be Submitted No Later than 990708 ML20207F2381999-06-0101 June 1999 Forwards Copy of Catawba Nuclear Station Units 1 & 2 1998 10CFR50.59 Rept, for NRC Files ML20195J1131999-05-26026 May 1999 Requests Approval to Change Cycle Dates for Two Year Requalification Training Program Required by 10CFR55.59,to Improve Scheduling of Requalification Exams to non-outage Periods 05000413/LER-1999-007, Forwards LER 99-007-00,re Operation Prohibited by TS 3.4.7. Commitments Identified in LER Are Listed in Planned Corrective Actions Section1999-05-26026 May 1999 Forwards LER 99-007-00,re Operation Prohibited by TS 3.4.7. Commitments Identified in LER Are Listed in Planned Corrective Actions Section ML20195B4751999-05-24024 May 1999 Forwards Rev 7 to UFSAR Chapter 2 & Chapter 3 from 1998 UFSAR for Catawba Nuclear Station.List of Instructions on Insertion Encl ML20196L1851999-05-20020 May 1999 Forwards Proprietary & non-proprietary Version of Rev 1 to TR DPC-NE-3004, Mass & Energy Release & Containment Response Methodology, Consisting of Finer Nodalization of Ice Condenser Region.Proprietary Info Withheld ML20196L1791999-05-20020 May 1999 Communicates Util Licensing Position Re Inoperable Snubbers. Licensee Has Determined That Structure of ITS Has Resulted in Certain Confusion Re Treatment of Inoperable Snubbers 05000413/LER-1997-009, Forwards LER 97-009-02, Unanalyzed Postulated Single Failure Affecting SG Tube Rupture Analysis, Suppl Revises Planned C/A Described in Suppl 1 to Ler.Current Status of C/As & Addl C/As Planned,Provided in Rept1999-05-17017 May 1999 Forwards LER 97-009-02, Unanalyzed Postulated Single Failure Affecting SG Tube Rupture Analysis, Suppl Revises Planned C/A Described in Suppl 1 to Ler.Current Status of C/As & Addl C/As Planned,Provided in Rept ML20206T4481999-05-13013 May 1999 Forwards Rev 3 to Topical Rept DPC-NE-3002-A, UFSAR Chapter 15 Sys Transient Analysis Methodology, IAW Guidance Contained in NUREG-0390 ML20206R1721999-05-13013 May 1999 Forwards Monthly Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 & Revised Monthly Operating Repts for Mar 1999 ML20206T0281999-05-12012 May 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual. Document Constitutes Chapter 16 of UFSAR 05000413/LER-1999-006, Forwards LER 99-006-00,re CR Ventilation Sys Inoperability. Root Cause & Corrective Actions for Occurence Are Being Finalized & Will Be Reported in Supplement Rept on 9906071999-05-10010 May 1999 Forwards LER 99-006-00,re CR Ventilation Sys Inoperability. Root Cause & Corrective Actions for Occurence Are Being Finalized & Will Be Reported in Supplement Rept on 990607 ML20206N8201999-05-10010 May 1999 Forwards Revs 15 & 16 to Catawba Unit 1 Cycle 12 COLR, Per TS 5.6.5.Rev 15 Updates Limits for New Catawba 1 Cycle 12 Reload Core & Rev 16 Revises Values Re Min Boron Concentrations for Rwst,Cla & SFP ML20206J4431999-05-0303 May 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual, Per 10CFR50.71(e).Document Constitutes Chapter 16 of UFSAR ML20206D2141999-04-29029 April 1999 Forwards 1998 Annual Radioactive Effluent Release Rept for Catawba Nuclear Station,Units 1 & 2, Per Plant TS 5.6.3. Rept Contains Listed Documents ML20206E4101999-04-26026 April 1999 Forwards Four Copies of Rev 9 Todpc Nuclear Security & Contingency Plan,Per 10CFR50.54(p)(2).Changes Do Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L5491990-09-14014 September 1990 Forwards Proprietary Response to Question Re Scope of Review of Topical Rept, Safety Analysis Physics Parameter & Multidimensional Reactor Transients Methodology, Per & 900723 Meeting.Response Withheld ML20059L5521990-09-14014 September 1990 Forwards Response to 18 Questions Re Topical Rept DPC-NE-2004,per NRC 900802 Request for Addl Info.Encl Withheld (Ref 10CFR2.790) ML20059K2021990-09-12012 September 1990 Submits Supplemental Response to Generic Ltr 89-14, Svc Water Sys Problems Affecting Safety-Related Equipment. Intake Structure Insp Program Developed.Procedures for Insp Implemented & Intake Structures Sampled & Analyzed ML20064A8041990-09-0505 September 1990 Notifies NRC of Mod to 890301 Response to Violations Noted in Insp Repts 50-413/86-18-01 & 50-414/86-18-01 Re Valves. All Valve Locking Mechanisms Would Be Installed by End of Unit 2 Refueling Outage (Approx Aug 1990) ML20064A5741990-09-0404 September 1990 Discusses Re Info to Support Util Position Relative to Resolving Issue of Main Steam Line Breaks Inside Ice Condenser Containments & Requests That Info Be Withheld (Ref 10CFR2.790) ML20059G3011990-09-0404 September 1990 Forwards Response to NRC 900327 Request for Addl Info Re BAW-10174, Mark-BW Reload LOCA Analysis for Catawba & Mcguire ML20059G8321990-08-30030 August 1990 Withdraws 880726 Proposed Tech Spec Change,Clarifying Tech Spec 3/4.7.6 Re Emergency Power Requirements for Control Room Ventilation Sys ML20059D2011990-08-27027 August 1990 Forwards Piedmont Municipal Power Agency , Authorizing Use of Annual Rept for NRC Docket Requirements ML20059D2441990-08-24024 August 1990 Forwards Special Rept PIR-1-C90-0261 on 900725 Re Cathodic Protection Sys Failure to Pass Acceptance Criteria of 60-day Surveillance.Std Work Request Generated to Check Voltage Potential at Test Station TS-36 on Weekly Basis ML20056B4981990-08-22022 August 1990 Responds to NRC Request for Addl Info Re General Relief Request for Pump Vibration Submitted 900315.Relief Request Changed to Insure Data Taken Over Range That Encompasses All Main Potential Noise Contributors ML20056B5011990-08-22022 August 1990 Responds to Violation Noted in Insp Repts 50-413/90-17 & 50-414/90-17.Corrective Actions:Review Will Be Conducted to Determine Category of Infrequently Run Procedures Needing Addl Verification Controls ML16259A2391990-08-22022 August 1990 Forwards Public Version of Rev 27 to Company Crisis Mgt Implementing Procedure CMIP-2, News Group Plan. W/ Dh Grimsley 900906 Release Memo ML20056B4971990-08-20020 August 1990 Clarifies Info Submitted in 871207 & s Re Steam Generator Tube Rupture Analysis Demonstration Runs. Demonstration Runs Met plant-specific Requirements in Section D to NRC SER on WCAP-10698 ML20059C1201990-08-20020 August 1990 Forwards Rept Summarizing Util Findings Re Three False Negative Blind Performance Urine Drug Screens Which Occurred During Jan & Feb 1990.Recommends That NRC Consider Generic Communication to Clearly State Reporting Requirement ML20059B6581990-08-17017 August 1990 Responds to Violation Noted in Insp Repts 50-413/90-15 & 50-414/90-15.Corrective Actions:Present Methods of Testing Operability of CO2 Fire Protection Sys Will Be Evaluated by 910201 to Determine If Addl Testing Necessary ML20059C1591990-08-17017 August 1990 Suppls by Providing Addl Info to Support Util Position Re Anl Confirmatory Analysis of Main Steamline Breaks in Ice Condenser Plants.Encl Withheld ML20063Q0951990-08-15015 August 1990 Forwards Monthly Operating Rept for Jul 1990 for Catawba Nuclear Station Units 1 & 2 & Revised Rept for June 1990 ML20059C1231990-08-15015 August 1990 Advises That Util Submitting Special Rept Re Valid Failure of Diesel Generator 2B Would Be Delayed Until 880229 Had Incorrect Ltr Date.Date of Ltr Should Have Been 880204 Instead of 880104.Corrected Ltr Encl ML20063Q2671990-08-14014 August 1990 Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 36 to CMIP-1,Rev 32 to CMIP-4,Rev 36 to CMIP-5,Rev 41 to CMIP-6,Rev 40 to CMIP-7,Rev 27 to CMIP-8 & Rev 35 to CMIP-9.W/DH Grimsley 900821 Release Memo ML20059C2211990-08-13013 August 1990 Forwards Revised Chapter 16, Selected Licensee Commitments Manual, to Plant Updated Fsar,Per 10CFR50.4 & 50.71.Manual Contains Commitments Which Require Control But Not Appropriate in Tech Specs ML20063Q0261990-08-10010 August 1990 Forwards Rev 0 to Catawba Unit 2 Cycle 4 Core Operating Limits Rept, Per Tech Spec 6.9.1.9 ML20063Q0671990-08-10010 August 1990 Submits Revised Response to Violations Noted in Insp Rept 50-413/90-09.Procedure to Verify Test Inputs Modified to Verify Dummy Input Signal to Channel RTD Circuit ML20058N0181990-08-0808 August 1990 Forwards Response to Request for Addl Info Re BAW-10174, Mark-BW Reload LOCA Analysis for Catawba & Mcguire ML20081E1601990-08-0101 August 1990 Advises of Completion of 900330 Commitment Re Standing Work Request for Insp of Air Flow Monitors & Dampers,Per Violations Noted in Insp Rept 50-413/90-03 & 50-414/90-03 ML20058P3261990-08-0101 August 1990 Forwards Public Version of Rev 26 to Station Directive 3.8.4, Onsite Emergency Organization ML20081E0951990-07-27027 July 1990 Forwards Decommissioning Financial Assurance Certification Rept for Duke Power Co,co-owner of Catawba Nuclear Station Units 1 & 2 ML20055H9741990-07-26026 July 1990 Forwards end-of-cycle 3 Steam Generator Insp Rept.Nineteen Tubes Removed from Svc by Plugging W/Rolled Mechanical Plug ML20055H5231990-07-24024 July 1990 Discusses co-licensee Relationship & Obligations Re Decommissioning Financial Assurance for Facilities ML20055H4571990-07-19019 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-413/90-11 & 50-414/90-11.Corrective actions:I-beams/ Hoists Rolled to Ends of Ice Condenser & Securely Located on Rails to Prevent Any Movement ML20055H1741990-07-18018 July 1990 Withdraws 880527 & 0725 Amends Clarifying Requirements for Containment Pressure Control Sys ML20055J3441990-07-17017 July 1990 Advises That Commitment Re Procedure IP/O/A/3190/01,per Violation in Insp Repts 50-413/90-06 & 50-414/90-06, Completed on 900619 ML20055H4131990-07-16016 July 1990 Forwards Public Version of Epips,Including RP/0/A/5000/07 & HP/0/B/1009/04 ML20055F8991990-07-13013 July 1990 Forwards Monthly Repts for June 1990 for Catawba Nuclear Station Units 1 & 2 & Operating Status Rept for May 1990 ML20055G2311990-07-13013 July 1990 Withdraws 880311 Proposed Amend to Tech Spec Table 3.3-3, Item 8.f Re Number of Instrumentation Channels Associated W/ Main Feedwater Pumps.Util Determined That Change Unnecessary ML20055F8461990-07-12012 July 1990 Requests 14-day Extension Until 900802 to Submit LER 414/90-010 to Investigate Power Supply Realignment ML20058P1231990-07-0707 July 1990 Advises That Commitment to Revise Maint Mgt Procedure 1.12 to Include Functional Verification Requirements & to Develop Retest Manual to Address Retest Requirements for Any Maint Performed on Components Completed on 900614 ML20055F4131990-07-0505 July 1990 Forwards Inservice Insp Rept Unit 1 Catawba 1990 Refueling Outage 4, Per 10CFR50.55(a)(q) & Tech Spec 4.0.5.Insp Performed Per Section XI of ASME Boiler & Pressure Vessel Code & Applicable Addenda ML20055D4291990-06-29029 June 1990 Supplemental Response to Violations Noted in Insp Repts 50-413/89-13 & 50-414/89-13,per .Personnel Responsible for Maintaining Crisis Mgt Ctr Drawing Trained. Util Will Continue to Evaluate Changes Made to Program ML20055E2191990-06-29029 June 1990 Submits Revised Commitment Dates Re Implementation of Dept Guidance on post-maint Testing,Per Commitment Made in 891002 Response to Violations in Insp Repts 50-413/89-19 & 50-414/89-19.Completion Date Changed to 900701 ML20044B0621990-06-26026 June 1990 Forwards Public Version of Revised EPIP HP/0/B/1009/05, Personnel/Vehicle Monitoring for Emergency Conditions. W/Dh Grimsley 900716 Release Memo ML20043H6921990-06-18018 June 1990 Advises of Revised Completion Date for VA Ductwork Cleaning to 901231,per Insp Repts 50-413/90-03 & 50-414/90-03. Vendor Personnel Assigned to Task Unavailable to Complete Cleaning Until Late 1990 Due to Outage Support Needs ML20043G1691990-06-15015 June 1990 Forwards Monthly Operating Repts for May 1990 for Catawba Nuclear Station,Units 1 & 2 & Corrected Monthly Operating Repts for Apr 1990 Re Personnel Exposure ML20055C8041990-06-15015 June 1990 Responds to NRC Re Violations Noted in Insp Repts 50-413/90-10 & 50-414/90-10.Corrective Actions:Instrument Root Valves Unisolated & Analog Channel Operational Tests for Low Temp Overpressure Protection Completed ML20043G4331990-06-13013 June 1990 Withdraws 900423 Proposed Amend to Tech Spec 4.6.1.8 Re Lab Test of Carbon Samples from Annulus Ventilation Sys ML20043G3771990-06-13013 June 1990 Withdraws 900423 Proposed Amend to Tech Spec 4.7.7 Which Required That Lab Test of Carbon Samples from Auxiliary Bldg Filtered Exhaust Sys Be Tested for Methyl Iodide Penetration of 0.71% ML20043G2511990-06-12012 June 1990 Withdraws 900419 Suppl to 871221 Application for Amends to Licenses NPF-35 & NPF-32 Re Tech Specs 4.7.6 Re Control Room Area Ventilation Surveillance Requirements ML20043G1741990-06-0707 June 1990 Responds to Request for Addl Info Re BAW-10174, Mark-BW Reload LOCA Analysis for Catawba & Mcguire. Correct RCS Operating Pressure Would Be 2,250 Psia as Identified in Table 3-1 ML20043G3451990-06-0707 June 1990 Forwards Proprietary Response to Request for Addl Info Re Topical Rept BAW-10174, Mark-BW Reload Safety Analysis for Catawba & Mcguire. Response Withheld ML20043G0721990-06-0707 June 1990 Responds to NRC 900510 Ltr Re Violations Noted in Insp Repts 50-413/90-09 & 50-414/90-09.Corrective Actions:Vc/Yc Train a Returned to Svc W/Supply Power from 2ETA.Terminal Box 1TB0X0346 Inspected & Insured Operable ML20043F6111990-06-0606 June 1990 Advises That Response to Request for Addl Info Re Operator Response Times During Simulated Steam Generator Tube Rupture at Facility,Will Be Delayed Until 900630 1990-09-05
[Table view] |
Text
. .
DUKE POWER Goxno.T P.O. HOX 33180 CitAMt.OTTE. N.C. 28242
- ", April 16, 1984 (' "
Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 2
Attention: Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: Catawba Nuclear Station Docket Nos. 50-413 and 50-414
Dear Mr. Denton:
Ms. Elinor G. Adensam's letter of April 10, 1984 transmitted three questions (as Enclosure 4) which were related to Open Item 5 in the Catawba SER, Thermal Design Procedures and Flow Measurement Techniques. A response to each of these questions is attached.
As the response to question 1 contains information proprietary to Westinghouse Electric Corporation, it is supported by an affidavit signed by Westinghouse, the owner of the information. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.790 of the Commission's regulations.
Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.790 of the Commission's regulations. Correspondence with respect to the proprietary aspects of the Application for Withholding or the supporting Westinghouse affidavit should reference CAW-84-33 and should be addressed to R. A. Wiesemann, Manager, Regulatory and Legislative Affairs, Westinghouse Electric Corporation, P. O. Box 355, Pittsburgh, Pennsylvania 15230.
Very truly yours, f.b. ff Hal B. Tucker ROS/php Attachment
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$$$"!!!SfoS$0$$$ /4 ) i E
r Mr. Harold R. Denton, Director April 16,1984 Page 2 cc: (w/o proprietary attachment)
Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission '
Region II 101 Marietta Street, NW, Suite 2900 l
Atlanta, Georgia 30303 i
NRC Resident Inspector Catawba Nuclear Station Mr. Robert Guild, Esq.
l Attorney-at-Law l P. O. Box 12097 l Charleston, South Carolina 29412 Palmetto Alliance 21351 Devine Street l Columbia, South Carolina 29205 1
Mr. Jesse L. Riley l Carolina Environmental Study Group l 854 Henley Place Charlotte, North Carolina 28207 l
l l
l
i l Quaation 1 1. In raaponce to ataffquestion 102.2 reganling tlw Improved & mal Decign Procedura (ITDP), your tatter of December 8,1982 providap a Weatinghouae raaponce regarding the variancca and diatributiona of coma ITDP paramatara, i.e., pracota'iact prcoatec, cora averaga temperature, reactor pcuer and reactor coolant flou. Even though tiu Wcatinghouac reaponsa raftcota tlw uco of EdF RTD trar:cmittora for Catauba, ottwr inntricnontation uncertaintica cited ara the gancria bow: ling valuca for Weating1xuaa inatrinantation. Plant-apecific instrinentation uncartaintica excacding tlw bote. ding valuco cited in tha Wootinghouac rcoponoa should be idantified and twod for tlw plant-apacific analycia. Pleaac identify any instrtrantation uhich daviatco from the Wcatinghouac inotrtrantation and provida the wwcrtainty valua partincnt to this inotrinentation and meactecment arrangement uith compartoon to the Wacting1xuca gancric value. & banca or couraca for tlw uncertainty valua should alco ha provided. & actwcca can be from purchaca opcatficationa, l
manufaattwing apecificationa, calibration data provided by inotrinantation vendor or obtained on cita, publialwd indtatry atandard or otiar justifiable bacca.
Fecnonso A cumory of the Catawh1 plant specific instrunentation for the precision heat balanco follows:
FIN LRCCRIAUtrY l
l Westinghouco Catasba Specific Referenco comenent Inntrunent Error Inntrunent Error Noten Fcedwnter Flow
~
l Venturi, K I* a,c 10.2% 1 AP and Road Out 10.08% of AP 2 i Feedwater Density I and Enthalpy
- a) Tarporaturo 10.63F 3 b) Proccuro 110 poi 4 Steam Enthalpy Steamlino Proccuro 23.3 psi 5
~ ~ '
Mointuro carrjover "'
6 Prin1ry Sido Enthalpy Tg (Electronica)
~
RTD Calibration ~AC 8 0
Scncor Drift DW
" 10.13r 9 e
FI m tR E RTAINTI Westinghouco Catawba Specific Camonent Ecforence Inntnnent Error Instrunent Error Noten TC (Electronico) _
Rr0 Calibration a,c a,c Senior Drift 8 l DW1 Accuracy
Iu2 U D G tores i
- 1 Aldon Ecscarch Iaboratories statanent of accuracy - 10.25%
- 2. Instnment Error:
Calibration Standard Accuracy a 10.008% of Reading
! 90-Day Stability (Drif t) = 10.004% Pull Scalo l DW1 Repeatability = 10.001% of Reading For a full scalo rango of S0 paid and a differential proccuro of 8.9 paid at
'75% power lovel, tho differential pressuro uncertainty la 10.0311.
10.031% 90 day total accuracy of Ruska DDR-6000 10.8001 Uncertainty for Procosa Fluctuation 10.048% Uncertainty for Singlo Instnment Randcm Error I
It0.88% of /.P 3.
nucuranonto will bo perfonned using a continuotm lead Typo-J thermoccuplo with an icel.uth referenco junction and a Fluko 2190A .Thennocouplc Thonxrnator.
Duko twor Comany Standards Lab Calibraticn Accuracy = 10.25 F l
l 1-Year Det Accuracy (Rafor to Attac! ment 3) -
= 20.58F l>rocons Pluctuations
= 10.014F Total Feedwater Ta@craturo Error s '
/frdT' 20.63F y 4 . . ,c; 4.
l Toot proscuro gaugo accuracy of 10.25% of r, pan 0 2000 psi span 10.25% x 2000 pai = 15 psig Additional concorvatita i for Drift = f 5 Lmiq E iTO psiig 5.
Dead Wolght Giugo Accuracy: 0.10% x 1000 pai=21.0 pai Proconn Fluctuation Errors i 1.3 pni Additional Concorvat:1tm for Drifts i1 Zi30 . 3pai_
pt.1 torts If a precinion digital prennuro gaugo in ucal to perfonn thin moacurunent, its accuracy will in an goed or tottor than tho thC.
h i
.= . .
1 6.
Same as the generic Westinghouse assuuption.
- 7. !
Pump power during the Calorimetric RCS Flow Test is measured by the plant process emputer and included in the calculations of RCS flow. The generic Westinghouse subnital assumes pump pcuer is an estimated valua.
8.
Same as the generic Westinghouse assumption. RrD's.are specified by Westinghouse Design' Specification Number 955322. Attachnent 1.
9.
The DVM used to measure hot and cold leg erd's is a Fluke 8520A, refer to Attachnent 2. The 90 day accuracy statement for this instrunent is:
[(0.007% (Input, .c) + 2 (digits)] '
DW Accuracy = [0.00007)(4500)+ 2 (.010)] = 0.05150-The ncminal output for the hot leg RrDs is 450 n.
The sensitivity to a change of the Rr0 or in resistance is AT the change in temperature with respect Frcm the Westinghouse design .
achms specification (Attachment 1) at 525 F the ncminal resistance.is 4100; at 625 F resistance equals 450.420. Therefore:
AT Ti-T2 625 F - 525 F 100 F %
. 5 nr -n2 450.420 - 4100'
- 40.420 = 2.5Wn The DVM error is:
i0.05150 x 2.5F/n = iO.129F I
1
~
The error of the DVM used to measure hot-h(T ) 'and cold leg (Tc) tmperature is the only generic plant specific Westinghouse cmponent that exceeds the bounding value of the subnittal.
Its effectc" however, is insignificant in the final detennination in the determination of TH and Tc is: of primary side enthalpy. The plant specific error W'. x l THand T -(Electronics) g. _. ~~
~
Calibration Accuracy
~
a,c -
Sensor Drift ~
,~
DVM , 10.131 ,.
TH and Tc Total Error I(e) = il.20 2F"~ ~
This cmpares to a generic bounding valuelof a,c.
- 2. Question y ,.. i-
'y - ~
p l' For the RCS flou measurement @the Westinghouse gerisric response states: >
within seven'daysif calibrating the measurement instrum drift effect& are'not included (except uhere necessary due to sinsor location)" .
Does yourinssr:anentation?
plant operating procedure have provisions that require the RCS fl measurement If not, what ars the drift uncertainty values associated process with each component such as LP Cell, local meter, RTD, themocou rack anksensors? ,
uncertainty? x What is the effect on the overall flow measurement
~-
- 4:- .M;
- 4. . -
-Resconse s .q ,
u
.? -
.a The following %y instnnentation is not calibrated
.e sithin?the specified seven (7)
Q ~
i 3;
. \ _ .. % , ,
i l
day period due to sensor location:
Pressurizer Pressure Hot and Cold Leg RTD's Sensor drift error is included in the Westinghouse analysis for these measured parameters.
The other measured parameters that are required in the' Westinghouse analysis to be calibrated within a specified (7) day period are:
Primary RTD Digital Voltmeter Feedwater Temperature Process Components AP Cell for Feedwater Flow The Digital Voltmeter used to measure the primary RTDs will be calibrated within seven (7) days prior to the perfomance of the precision heat balance.
The feedwater temperature is measured by precision test Type - J themocouples which are of higher quality than the process temperature sensors referenced in the generic submittal. These themocouples are regularly calibrated and equipment histories indicate the 0.25F calibration accuracy, providing-the ther-moccuple is not physically abused is The accuracy quoted for the Digital Themogood couplefor the annual includes Themometer calibration an cycle.
annual drift alkwance.
The feedwater flow AP is read by the Ruska DDR-6000. The accuracy previously quoted in question 1 was a 90-day specification that included an allowance for instrument stability (drift). A calibration check on the Ruska DDR-6000 will be perfomed within 90 days of perfoming the precision heat balance.
Provisions will be included in the procedure for insuring the calibration of.
these instruments within the specified period.
- 3. Question i The Westinghouse report states:
i "It is also assuned that the calorimetric flou measurement is performed at the beginning of a cycle, so no allouance has.
been made for feeduater venturi crud buildup"[and "If venturi fouling is detected by the plant, the venturi should be cleanedi prior to perfomance of the measure-ment. -If the venturi is not cleaned, the effect of the fouling on the feeducter'.
flou, should be measured and treated as a bias, i.e., the error due to venturi .
fouling should be added to the statistical sumnation of the rest of the measure-ment errors".
a) ^ Hou do you assure that the venturi is clean at' the beginning of a cycle? ;
. Is the venturi cleaned at the beginning of every cycle? l b) Hou do you detect the venturi fouling and to what extent [of-uncertainty can you detect fouling? - _.
c) ~ Describe the design provisions 'and procedures to clean the venturi if _ -
fouling is~ detected. ^
d) Hou do you determine the error on feeduater flou measurement due to the
, . fouling effect if the_ ' venturi is not cleaned or if the venturi fouling is not detected?.
4 :
l l
i
., l
e) If the venturi is not cleaned prior to the calorimetric flou measurement because no fouling is detected, an error component should be added. The magnitude of the error component should depend on the minimi.m detectable value of fouling.
Response '
(a and c) The feedwater venturis will be assured to be clean by benchmarking trended parameters at the beginning of the first fuel. cycle. Presently, no provisions cycle. exist for cleaning the feedwater venturi at the beginning of every (b, d, and e) The Catawba Perfomance Monitoring Program includes a monthly review of trended data conducted for the purpose of detecting potential venturi fouling. The undetected development of venturi fouling during a power cycle would introduce a non-conservative bias into any subsequent efforts to nomalize the RCS elbow tap flow indications. The monthly review includes analyzing trended data of electrical output, feedwater flow and 1st stage pressure.
The ratios of electrical output and 1st stage pressure to feedwater flow would shift in the event of venturi fouling and are, therefore, monitored to detect fouling. Indicated reactor themal power is directly porportional to indicated feedwater flow. Venturi fouling would result in an increase in indi-cated feedwaer flow which would increase indicated reactor themal power. Since the reactor themal power is limited to the 100% licensed value, indicated feed-water flow is also limited and actual feedwater flow would be reduced. By reducing actual feedwater flow, electrical output and 1st stage pressure are reduced;by the same degree. Therefore, by trending electrical output and 1st stage pressure with indicated feedwater flow, venturi fouling can be detected.
The nomal relationship between electrical output,1st stage pressure and indicated feedwater flow will be established during the first fuel cycle when the venturi is presumed to be clean. To avoid any significant effect of measure-ment uncertainties on the results, the monthly review will include analyzing data that is trended on a daily basis. The mean electrical output and mean 1st stage pressure will be compared to the mean feedwater flow. If the trend of the monthly reviews indicate that this ratio has deviated by 0.1%, corrective action will be taken before performing the next precision heat balance for RCS flow measurement.
Corrective action will involve either (1) inspecting and cleaning the venturi or (2) quantifing the bias effect of the fouling and making an allowance for it in the RCS flow measurement.
The taken. 0.1% value serves as an " alarm level" at which corrective action must be This value was chosen because it is believed to be high enough to avoid fouling. "alams" yet low enough to avoid an unnecessarily excessive penalty for spurious t
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$ 8520A/8522A j~ ,, /M ,. Ld =6 43 i f
Blas Current: G50 pA Accuracy: i(Co of Inp t + Digits)
Maximum Reading Rate s0 Days 1 Year Plus Temp
- Range 24 Hours 18*C, 18'C Coefficient operation Line Rate Resolution 23*C i 1*C Y328'C 28'C per *C*
i 50 Hz 200 rags /sec*
- Local or 5% digits 100 0 0045 + 6 0 0080 + 7 0.0140 + 12 0 0007 + 2 0
} Remote 60 Hz 1000 0.0035 + 2 0.0070 + 2 0.0125 + 3 0 0007 + 0 2 240 rdgs/sec*
10000 0 0035 + 2 0.0070 + 2 0.0125 + 3 0.0007 + 0 2 50 Hz > 500 rdgs/sec 10 kO 0 0035 + 2 0 0070 + 2 0 0125 + 3 0 0007 + 0 2 Remote 4% digits 00 Hz > SM rdgs/sec 100 k0 0 0040 + 2 0 0090 + 2 0 0140 + 3 0.0012 + 0.2
- For localoperation,8522A us tam red to % this rate. 1MO O 0090 + 2 0.0160 + 2 0 0200 + 3 0.0020 + 0.2 30 ya O_0300 + 1 0 0440 + 1 0 0450 + 3 0.0030 + 0 2 AC Voltage (True RMS) *From r8*C to 0*C or 28*C to 50*C Input Characteristics Conductance .
Range Full Scale R esolution input impedance Range: 100 nS (10 MO) ' '
tv i.99999 30 yv Full Scale: 199.99 -
10V 16.0100 100 SV 1 MO. s; 100 pF Resolution: 0.01 nS (100,000 MO) i
[y 1,30 30 00 kvv Accuracy: (To of input + Digits) 90 oays 1 Year *Plus Temp Accuracy: i(Fo input + Fo of Full Scale) ac or ac+dc e 24 H
,C *C 2 28 C pe 90 oays 1 Year 0 04 + 5 0 05 + 5 0 06 + 5 0 004 + 1 18'C to 28*C 18*C to 28'C
.From 18*C to 0*C or 28 C to 50*C Frequency % of +% FS +% FS % of + % FS +% FS anput AC AC+oC input AC AC+0C Maximum input: 400V peak 10 Hz to 20 Hz" 3.0 0.6 0.7 3.5 0.6 0.7 Maximum Reading Rate: 10 readings per second 20 Hz to 40 Hz** 0.5 0.5 0.6 0.6 06 0.7 40 Hz to 20 kHz 0.1 0.03 0.08 0.15 0.05 0.16 External Reference 20 kHz to 100 kHz 1.0 0.3 0.4 2.0 06 0.8 Operating Range: 0.5V de to i33V de as long as external 100 kHz to 300 kHz 2.4 0.6 06 40 0.1 0.1 reference Low terminal is within il6.5V ofinput Low terminal 300 kHz to 1 MHz 8.0 2.5 2.5 15.0 5.0 50
- From 0.1% of range to fuit scale input Impedance: 10.000 M n between external reference liigh
- Wath statistics program for smoothing or Low terminals and input Low terminal Accuracy Temp. Coefficient: 18 C to 0 C or 28'C to 50'C, to 20 kitz x. Ret voitage Accuracy AC Mode: (0.007Po ofinput + 0.0077c FS)/ C 16 Sv to 33v 2( A + B + 20 ppm >
AC+DC Mode: (0.007Fe of input + 0.0149' o FS)/'C 0 SV to 16 5V (A + B + (400 ppm + IVrefI)]
Maximum Input: 1000V peak liigh to Low or Guard to Note. A = oC 10 voit tange accuracy Chassic terminals, and 200 V peak Guard to Low terminals s - input voltage or resistance range accuracy Crest Factor: ;>4:1 at full scale, increasing down scale Maximum Reading Rate: 10 readings per second Maximum input: 180V peak between external reference liigh Maximum Stew Rate: 177V per us or L w and input Low; 360V peak between externa reference Maximum Volt-Hertz Product: 2 x 107 liigh and Low Resistance Transfer Accuracy ,
Input Characteristics The following accuracy specifications apply when:
. Reading rate is 2 readings per second Current open Circuit . Filter settling time is $00 ms Range Full Scafe Resolution Thrt, ugh Unknown Voltage . Warm-up is at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 100 19 9999 100pO 10 mA IMO 199 999 1m0 10 mA . Quantity measured has same nominal value and frequency as IriOO 1999 99 10 m0 1.0 mA transfer standard 10 kQ 19 9999 100 mO 0.1 mA 7V . Measurements are made in one range
. ~ kQ 199 999 10 14 5 pA (max) . Standard is checked at least every hour 1MO 1 99999 10 0 1.5 uA (man) 10 MO 19 999 1kO
. Ambient temperature remains within il*C 1.5 uA (man)
, DC Voltage AC Voltage (all ranges)
Maximum Input: 400V peak for any range f gg ,, ,,,,, , 1 gg ,, ,,,,, .
Maximum Reading Rate: 100 kn range and higher, reading Range digits) Frequency rate is 10 rdgs/second % of Futt scale)
" 100 mv 0 0020 + 4 10 Hz to 20 Hz 10 + 0 2 10 kn Range and Lower IV 0 0020 + 1 20 Hz to 40 Hz 0.1 + 0.1 10v 0 0010 + 1 40 Hz to 20 kHz 0 005 + 0 009 Operaten Resolution Line Reading Rate 0 M 20 + 1 20 mz to W mz OM + 0 030 1000V O 0020 + 1 100 kHz to 1 MHz 0 500 + 0 60 Local or 5 %-digits 50 Hz 2M rdgs/sec*
Remote 60 Hz 240 rogs/sec*
Remote 4 %-digits 60 Hz >500 rdos/sec
- For local operation. 8522A ns Ismoted to 'o this rate -
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DIGITAL THERMOMETEPiS 2180/2190 Series Thermometer Specifications Lead Resistance: 4-wire: 2000 max per lead for both 1000 2190A Thermocouple Thermometer Specifications and 100 RTD's; 3-wire: 20 max per lead for 1000 RTD's, Thermocouple Types: Five, switch selectable. Which thermo- 0.180 max per lead for 100 RTD's; 2-wire: 0.90 max perIcad couple types depends on your choice of microcomputer type. for 1000 RTD's,0.090 max per lead for 100 RTD's See Accuracy chart below Lead Resistance Error:4-wire: no error:3-wire 1000 RTD's:
Resolution: 0.l*C or *F 0.012' per degree per ohm: 3-wire 100 RTD's: 0.12* per degree input Connection: 2 wires on screw terminal isothermal block per ohm: 2-wire 1000 RTD's: 0.025' per degree per ohm: 2-wire Max Source Impedance: 2 kn 100 RTD's: 0.25* per degree per ohm Overrange Detection: Flashing display 2180A Linearizations (Microcomputer Type 2).
Open Circuit Detection: Source impedance of 3 kn or more causes a flashing "OC" RTD Type Linearization Coetriciente 100 0 385 Pt DIN" 43760 Taoie 2190A Accuracy
0 0038994 1000 DELTA * =
Maximum Error
- 390 Pt 1.494 Thermocouples 2 Degrees C A4' =
-0 265668 x 10
- IDegrees F Applicabfe 90 1 90 1
- Portion of Days Year Days 100 0 Type Temperature Yost DELTA * =
1.505 20*C 15*C 68*F 59'F 3916 Pt A4' Range =
At to to At to -0 099668 a 10 5
'C to C4* =
-0 271142 x 10M Cal 30*C 35*C Cal 86*F 95'F Microcomputer Type 1 ALPHA * =
0 00339221 1000 DELTA * =
J -128 to 0 0.18 0.19 392 Pt 1 493 0 21 0.20 0 23 0 26 A4' =
0 to 900 0 18 -0 38668 x 10 5 0 31 0 36 0 20 0 47 0 58 C4' =
+0192912 x 10M K 132 to 0 100 0 0 18 0.19 0 21 0 30 0.33 0 37 DIN" 43760 Table 0 to 1350 0.18 0 39 0 47 0 30 617 Na 0 72 087 T -243 to 0 0.18 100 0 20 0 22 0 30 0 35 0.39 RO '
O to 400 0.18 Cu 9 042 Ohms 0 22 0 25 0 30 0 41 0.46 R25 =
R AL.pHA 10 005 Ohms 0 to 1708 0 31 059 0 70 0 47 =
0 004260 D 1 01 1 20 C" O to 2471 0 18 060 1 0.75 *See IPTS 68 ens.atoons on NBS Monograph 126. Microcomputer Type 1 no 0 30 1.11 1.37 fonger avadaele.
Microcomputer Type 2 ##
J -128 to 0 0.18 0.19 0 21 0 20 0 23 j 0 26 O to s00 0 18 O st 0 36 ruo 047 1 058 2180A Accuracy (Microcomputer Type 2)*
K -132 t0 0 0 18 0 19 0 21 0 30 0.33 0 37 O to 1350 0 18 0 39 0 47 C 30 0 72 0 87 Manimum Error
- E -252 to 0 0.18 0 20 0.22 0.30 0 35 "
O to 1000 0.18 0 33 0 39 0 40 ''" * "
0 30 0 61 0.72 Applicable R 0 to 1708 90 1 90 0 31 059 0.70 0 47 1.01 1 20 Portion ot Days 1
S Type Year Days Year O to 1685 0.22 050 1 0 60 0.38 , 0 92 Temperature 20*C 1.10 15'C 68'F 59'F Microcomputer Type 3 Range At to to At to to
- C Cat 30*C 35'C Cal J -100 to 0 0.18 0 19 86*F 95*F DIN"* 0 20 0.30 0 32 0.36 -190 to 0 O to 760 0 18 0 28 0 33 0 043 0 089 0 112 0.076 0.161 0 30 0 52 0 61 1000 0 to 204 0 203 K 0 043 0.132 0.173 0 076
-50 to 0 0 18 0.18 0 20 0 239 0.314 0 20 0 22 0 25 385 190 to 0 0.11 0 to 1372 0 18 0 39 0 48 0 20 Pt 0 12 0.14 0.18 0 21 0 24 0 63 0 78 0 to 750 0 11 T 0 26 0 37 0 18 0 46
-200 to 0 0.18 0.20 0 21 0 33 0 34 0 62 DIN" 0 38 -200 to 0 0 009 0 055 0 078 0.015 O to 400 0 t8 0 22 0 25 0 30 0 100 B
0 41 0 46 100 0 0 to 204 0 009 0 098 0.139 0 015 0.177 0.142 420 to 1815 0 21 0 52 0 62 0.37 0 95 390 0 252 1.15 -200 to 0 0 08 0.10 0 11 A 140 to 1700 Pt 0.13 0.16 0.19 0.18 0 46 0 46 0 20 0 74 0 to 750 0 08 0 93 0 23 0 32 0 13 0.41 0 57
-200 to 0 0 040 0.086 0.109 0 071
- TotalInstrument accuracy. Does notinclude Thermocouple errors such as non-conformity to standard curve.
- O '* 20" 0^0#0 M3 U' 0 156 0.198 O CI' O 234 0 309 3916 -200 to 0 "C cesignates Tungsten-5% Rhenium vs. Tungsten-26%e Rhenrum. 0 11 0 12 0.14 0.17 0 21
'" DIN is a European Standard. P1 0 to 150 0 10 0 24 0 26 0 34 0 17 0 46 0 62
-200 to 0 0 008 0 055 0 078 0 014 2180A RTD Thermometer Specifications 1000 0 to 204 0 099 0 141 0 009 0 098 0.139 0 014 0.177 392 0252 RTD Types: 1000 Pt 385 (DIN),390,3916, or 392; 1000 Nt .
-200 to o 0 08 0.10 0 11 0 12 Pt 0 to 750 0.16 0 19 (DIN); 100 Cu; O to 9990 resistance - s3 itch-selectable 0 08 0 23 0 32 0 12 0 41 0 57 Resolution: 1000 Pt RTD's: 0.0l*, autoranging to o.l* above -60 to 0 0 129 0.157 0.172 0 230 0 282 0 308 1000 010 93 0 129 0.176 0 199 0 231 0 317 204* C; 100n Ni RTD's: 0.0l*, autcranging to o. l* above 93* C; egy 0 359 100 Cu RTD's: 0.l* 60to0 0 19 0 20 0 2t 0 33 0.35 Input Connection: Ne Oto 177 0 19 0 22 0 25 0 33 0 39 0 35 4-wire screw terminals. Terminals accept 100 0 44 3-wire and 2-wire RTD's at reduced accuracy -75 to 0 0 16 0.18 0 19 0 27 Cu 01o 150 0 16 0 20 0 23 0 31 1034 RTD Matching: User-performed potentiometer adjustment 0 27 0 35 l 04 t Ohms O to 196 99 0 005 matches the 2180A to user's RTD to compensate for variations 0 042 0 059 Alt units in lead length and resistance at 0*C O to 999 99 0 05 0 22 0 31 en Ohms NOTE: Shaded area is 0.01* resolution; unshades area as 0. t
- Total unstrument sceuracy. Does not include R TD probe errors. Valed for 4-wore RTO's only. Mocrocomputer Type 1 no longer avadable.
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