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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 GOMPANY P.O. 390X 33189 CHARLOTTE, N.O. 98949
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USIEEt September 11, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. B. J. Youngblood, Project Director PWR' Project Directorate No. 4 Ret Catawba Nuclear Station Docket Nos. 50-413 and 50-414 Dear Sir On August 1,1986, Duke Power Company submitted a response to the Staff's Safety Evaluation Report on Operability / Reliability of Emergency Diesel Generators Manufactured by Transamerica Delaval, Inc. The purpose of that letter was to address plant specific itema identified in the SER. As a result of discussions with the Staff, please find attached information to supplement the August 1, 1986 submittal.
Very truly yours, C.- g b, 4 Hal B. Tucker ROS/15/ sib Attachment xc Dr. J. Nelson Grace, Regional Administration U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 NRC Resident Inspector Catawba Nuclear Station 0609100107 86071' PDR S
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Duke Power Company Catawba Nuclear Station Response to NRC Question on TDI D/G's References
- 1. Letter from H. B. Tucker to H. R. Denton, June 29, 1984, forwarding 1A inspection report.
- 2. Letter from H. B. Tucker to H. R. Denton, Oct. 6,1984, forwarding 1B inspection report.
- 3. Letter from H. B. Tucker to H. R. Denton, Oct. 2,1985, forwarding 2A inspection report.
- 4. Letter from H. B. Tucker to H. R. Denton, Dec. 23, 1985, forwarding 28 inspection report.
- 5. Letter from H. B. Tucker to H. R. Denton, June 21, 1985, providing resolu-tion of DRQR items on CNS 1A D/G.
- 6. Letter from H. B. Tucker to H. R. Denton, Jan. 13, 1986, providing resolu-tion of DRQR items on CNS 2A, 2B D/G's.
- 7. Letter from H. B. Tucker to H. R. Denton, May 19, 1986 providing resolution of 09QR items.
- 8. Letter from H. B. Tucker to H. R. Denton, August 1,1986, addressing the TDI Generic SER.
- 9. Letter frcia H. B. Tucker to H. R. Denton, August 6,1986, addressing Catawb3 Opn cting License requirements on TDI Diesel Engines.
- 10. Review of .tesolution of Known Problems in Engine Components For Trans#merica DeLaval Inc. Emergency Diesel Generators, PNL-5600, Dec. 1985.
- 11. TDI 91est! r ' .arator Design Review and Quality Revalidation Report, Appen-dix .I R e't . :, April 1986.
- 12. Safety ~ valuation Report - Operability / Reliability of Emergency Diesel Generatu s Manufactured by Transamerica DeLaval, Inc. (NUREG-1216)
- 1. NRC Question.;
Verify that the Design Review and Quality Revalidation (DRQR) requirements have been addressed on all Catawba Nuclear Station (CNS) Emergency Diesel Generators (D/G)
DPCo. Response: DROR Inspections DPCo. considers that all of the requirements of the TDI Owner's Group DRQR Inspection Program have been addressed. This is discussed in general terms below and in detail in the references provided.
CWH:09:05:86:B3
. Page 2 question No. 1 Continued The inspection of the CNS 1A D/G was completed before the TDI Owner's Group DRQR Program-was developed. Reference 1 provided the scope and results of this inspection. This program was reviewed by the NRC and its consultants and found to be acceptable. DPCo. provided documentation and justification of the differ-ences between the CNS 1A program and the TDI Owner's Group DRQR in Reference 5.
CNS 1B D/G inspection was also completed prior to the development of the DRQR.
The 18 D/G was considered a . follow engine in accordance with general DRQR criteria. As a follow engine less stringent inspection requirements were applied to the D/G based on the favorable results of the 1A D/G inspection. The scope and results of this inspection were reviewed and approved by the NRC and their PNL Consultants.
CNS 2A and 28 D/G were also considered to be follow engines. The inspections on these engines were conducted in accordance with the DRQR since it was available when these were carried out. References 3 and 4 provided the results of these inspections. There were some differences between the CNS 2A, 28 D/G inspections and the DRQR. These are discussed in detail in Reference 6.
OPCo. Response: DRQR Modifications ,
All modifications recommended by the DRQR will be accomplished by the end of the first refueling outage with the exception of those noted in References 5 and 7.
Detailed justification for these exceptions is provided in the references.
- 2. NRC Question:
The NRC expressed a concern that the 5 year Appendix II requirement could be exceeded due to the variations in fuel cycle lengths.
DPC3. Response:
The definition of the frequencies is provided in Reference 1, Part A, Page II-A-3. This definition accounts for the variation in fuel cycle length.
- 3. NRC Question:
Provide a status on Items B, I, K and 0 in Attachment I of Reference 11.
DPCo. Response:
Item B: Auxiliar3 Module Wiring and Terminations Action Required: Verify that the States sliding link terminal blocks were not manufactured between 1974 and 1976.
DPCo. Status: The manufacture date for the States sliding link terminal blocks on the generator control panel have been investigated. All of the States CWH:09:05:86:B3
Page 3 Question No. 3 Continued' sliding link terninal-blocks installed on this equipment were purchased by RTE Delta on or after June 27, 1978. Documentation of the exact manufacture date is not available. However, the supplier stated that inventories of greater than 6 months have never been maintained on these components. On this basis there is a very low probability that these sliding links were manufactured in the 1974 to 1976 period. Other panels associated with the engine do not utilize States sliding links.
Item I: Engine Base and Bearing Caps Action Required: Take replicas of the CNS 1A and 1B engine bases prior to the end of the first refueling outage (RFO). Other actions required in this item apply to Unit 2 engines only.
OPCo. Status: Replicas are being taken of both the CNS 1A and IB engine bases. i These will be evaluated before the end of- the f*.rst RFO. Any degenerate Widmanstaetten structure detected will be addressed and reported to the NRC in accordance with the SER.
Item K: Jacket Water Pump Action Required: Verify the torque on the nut holding the external spline to pump shaft is a minimum of 120-ft-lbs. on CNS IB D/G.
OPCo. Status: The torque on the CNS IB D/G jacket water pump will be verified to be a minimum of 120-ft-lbs prior to the end of the first RF0.
Item 0: Turbochargers Action Required: Replace the CNS 1A D/G turbocharger bracket bolting by the end of the first RFO.
OPCo. Status: The CNS 1A D/G turbocharger bracket bolting has been replaced.
- 4. NRC Question:
The TDI SER required quarterly ferrographic analysis of engine oil while the 0wner's Group Maintenance and Surveillance Program, Appendix II requires ferro-graphic analysis only when the monthly spectrographic analysis indicates a need.
DPCo's response on these items differed. Provide resolution.
OPCo. Response:
Currently spectrographic analysis is conducted on a monthly basis and ferro-i graphic analysis is conducted on a quarterly basis. This practice will contin-ue. On this basis the response provided to the SER in Reference 8 Attachment 1, Item 0.3. is amended to read.
"A ferrographic analysis will be conducted on a quarterly basis."
CWH:09:05:86:B3
Page 4
- 5. NRC Question:
The Maintenance and Surveillance Program Appendix II Rev. 2, Part No. 02-315A Page II-D-CAT 3 Item I was changed by Reference 8 Attachment 1, Item' F. The recommended change should be included as an additional Maintenance and Surveillance Matrix item or as a comment.
DPCo. Response:
The change recommended in the above letter will be included as a comment on Item 1, Part No. 02-315A Page II-D-CAT 3. The original Item will be left as is. This change will be made in accordance with existing company procedures for changing controlled documents.
- 6. NRC Question:
The TDI Diesel Generator Design Review and Quality Revalidation Report, Appendix II Rev. 2 port E contains the engine part number cross reference. Some compo-nents were left blank for CNS. Provide a description of the surveillance DPCo.
plans on these components.
DPCo. Response:
DPCo. will perform maintenance on those components without numbers in the cross reference (TDI DRQR App. II Part E) per the table below. The components in the table harq missing part numbers due to 1) the CNS engines do not have the part or 2) the part was purchased from a vendor other than TDI.
Comanchee Peak' CNS Maintenance Part Description Part No. Follows App. II Rev. 2
, Air start block valves 03-441B Yes l
Aux. Sub-Base & Oil & Water Piping 02-717C Yes Jacket Water: Pipe, Couplings, Fittings, j etc.
. Aux. Sub. L.0. Pipe & Fittings 02-717F Yes l
Aux. Sub-Base L.O./F.0. Valves02-717 G/K Yesi ,
Barring Device Air Filter 02-525C Do Not'Have l Barring Device Control Valve / Pressure 02-525B Yes -
Regulator Control Valve Only l
i
- Crank Case Vacuum Fan 02-387A Do Not Have Diesel Starting Air Compressors 02-835B Yes
! Emergency Generator Control Panel CP-102 Yes CWH:09:05:86:B3 w - - - -ye. -
Page 5 Question No. 6 Continued Comanchee Peak CNS Maintenance Part Description part No. Follows App. II Rev. 2
- Fly Wheel Bolting 02-330B Not in Matrix Gear Train None Yes- Inspected per App. II while inspecting other components e.g. cam, crankshaft, governor, Hydraulic Valve Lifters 02-390F Do Not Have
~
Jacket Water Fittings, Pipe. 02-435A Yes (Small Bore Only)
Jacket Water Stand-pipe & Misc. 02-700F Yes Bolting L.0. Keep-warm Strainer 02-800D Yes- Same as 02-820D Should have been 02-8200 Piping System No Number Yes
- No Comanchee. Peak Number was assigned. Part number listed was for Shoreham Nuclear Station D/G. No requirements were listed in the matrix for the Flywheel or the Flywheel bolting. This bolting was inspected on the lead engine as part of the DRQR.
t 7. NRC Question:
l For those items in the DRQR Appendix II, Rev. 2 where the frequency is not specifically given, provide frequency. (List of components was provided during l
8/21/86 phone call between DPCo. and NRC)
DpCo. Response:
l The list of components provided has been reviewed and a specific definition of the frequency for performing each item is given in the table below.
Part Part Problem Number Description Definition problem Disposition 02-425A Jacket Water Define Frequency Recommended torque values in Pump gear - Item 3 Item 3 have been incorporated in the maintenance procedures for the jacket water pump.
These procedures are used when maintenance is performed on the pump.
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Page 6 Question No. 7 Continued Part Part Problem Number Description Definition Problem Disposition F-068. Intercoolers Define Frequency Intercooler shell and tubes
- Item 2 will be inspected and cleaned whenever monthly temperature readings indicate that fouling has occurred.
CP-102 Emergency Define Frequency 48 Months.
Generator - Item 5 Control Panel 02-371A Fuel Pump Define Frequency 6 Months.
Control Shaft - Item 1 02-410C Overspeed Trip Status of L-110 The L-110 Lovejoy coupling Drive Coupling Lovejoy have been replaced in replacement. accordance with SIM363.
02-455B Fuel Oil Define Frequency Air is purged from the stand-Strainers - Item 2 by strainers whenever a high pressure drop is indicated during accomplishment of Item 1.
02-500A Engine Control Define Frequency Elastomeric parts are replaced Cabinet - Item 5 when results of system test indicate ' control air pressure is not being maintained within prescribed limits.
02-500C Circuit Breakers Define Frequency 36 Months.
and Contact - Item 3 Blocks 02-525B Barring Device Define Frequency When leakage occurs.
Control Valve & - Items 1 & 2.
Pressure Regulator 02-525C Barring Device Define Frequency N/A at CNS.
Air Filter - Items 1 & 2 02-540C Lube Oil Sump Define Frequency 18 Months.
Tank - Item 3 02-6300 Thermocouples Define Frequency 18 Months.
- Item 2 CWH:09:05:86:B3
Page 7 NRC Question No. 7 Continued Part Part Problem Number Description Definition Problem Disposition 02-695B Engine Control Define Frequency The engine control air Air Pressure - Item 2 pressure regulator will have Regulator elastomeric parts and gaskets replaced whenever inspection required in Item 1 indicates degradation.
02-695C Engine Control Define Frequency 18 Months.
Pneumatic Trip - Items 1 & 2 Switches 02-700B Jacket Water Define Frequency When leakage occurs.
Stand Pipe Valves - Item 1.
02-717GK Auxiliary Sub- Define Frequency When leakage occurs.
Base L.0./F.0. - Item 1.
Valves 02-810C Jacket Water Define Frequency When Item 4 is done.
Heat Exchanger - Item 5 02-810D Thermostatic Define Frequency The thermal power elements Valves - Item 1 will be replaced when during the monthly test degradation is indicated.
02-810E Jacket Water Define Frequency 18 Months.
Heaters - Item 1 02-820A L.O. Sump Tank Define Frequency 18 Months.
Heaters - Item 2 02-820F Full Flow L.O. Define Frequency 12 Months.
Filters - Item 3 02-820G L.O. Heat Define Frequency When item 3 is done.
Exchanger - Item 4 02-820H Full Pressure Define Frequency 18 Months L.0. Strainer - Item 3 02-835J Starting Air Define Frequency 18 Months.
Storage Tank - Items 2 & 3 CWH:09:05:86:B3
Page 8
- 8. NRC Question:
Provide .a response _ to the optional and suggested actions provided in the SER.
(A list was provided by the NRC during 8/21/86 phone call).
DPCo. Response:
The optional and suggested items included in the SER have been reviewed. These items are addressed in the table below:
SER SER PNL Section Pg. # Section SER Recommendation DPCo Response 2.1.3.4 2-6 4.5.4.2 Increase main lube oil A joint program between pressure 10%. DPCo. and TDI has indicated that the L.0.
pressure regulating valves installed on the '
engine will not allow increased pressure operation. However, all
, problems-experienced with the engine L.O. system to date have been adequately addressed by the turbo-charger prelube modifica-
. tion. On this basis DPCo.
will not increase main L.0. pressure.
2.1.3.4 2-6 None PNL recommendation to DPCo. concurs with the OG extend the critical findings with respect to zone of R.T. all- the the R.T. zone and will way to_the bearing continue to R.T. in end vs. 1/4 in from accordance with original end as originally OG plan. In addition required by the OG. this recommendation i
applied to 8 cylinder engines only.
I 2.1.3.7 2-7 4.4.4.4.1 U.T. of DSRV connect- DPCo. has incorporated ing rod pre and post U.T. extension measuring tensioning. of con rod bolting in the maintenance procedure for this component.
2.1.3.7 2-8 4.4.4.4.2 Inspection of con rod ECT will be used to bolt holes should be inspect the con rod bolt by (1) ECT, (2) holes. An alternate alternate method method of equal equivalent to ECT. sensitivity is under NRC development.
I CWH:09:05:86:B3
Page 9 Question No. 8 Continued.
SER SER PNL Section Pg. # Section SER Recommendation. DPCo Response 2.1.3.8 2-10 None Actions should be Cautions have been added taken to prevent to the DRQR App. II and sustained engine to operating procedures operation in an un- to' prevent unbalanced balanced condition. operation. See H.B. Tucker's letter to H.R. Denton, Aug. 1, 1986, Att. 1,-Para. E.
2.1.3.11 2-13 4.7.8.3 Revise the DRQR App. The DRQR App. II Part D II plant specific will be modified to section.to require an include the required inspection of the inspections at the 10 yr.
crankshaft at 10 yr. overhauls.
overhaul vs. 5 yr. 1 time.
2.1.3.11 2-13 4.7.9 Complete DRQR require- The requirements of the ments including DRQR have been completed torsiograph, material for the CNS 1 engines certification and including these preservice crankshaft recommendations.
inspections.
2.1.3.13 2-16 4.9.5.2 Inspection of blocks DPCo. engines have with known or assumed neither known or assumed lig.~ cracks at each cracks. DPCo. will RF0 in accordance with inspect the block in PNL recommendations. accordance with the DRQR App. II Part D, which incorporates the PNL 5600 requirements.
2.1.3.13 2-16 4.5.9.2 Visual inspection of DPCo. believes that the block under intense inspections required by light. Inspections of DRQR App. II Part D the liner and cam will be adequate to gallery and M.T./ECT detect block cracking.
per PNL.
2.1.3.13 2-15 4.9.5.2 Recommendations on the DPCo. believes that the inspection methods for inspection procedures and block tops. acceptance criteria currently in use are adequate to ensure reliable engine opera-tion.
CWH:09:05:86:B3
Page 10 NRC Question No. 8 Continued SER SER PNL Section Pg. # Section SER Recommendation DPCo Response 2.1.3.13 2-17 4.9.5.2 Do not put any engine DPCo. examined the micro-with degraded micro- structure of all of the structure into service CNS engine blocks and has without providing no degraded justification to NRC. microstructure on any engine.
2.1.3.14 2-18 4.10.4.3 Do not put into All CNS cylinder heads service any cylinder with weld repairs from heads with repairs to one side only have been the injector bore hole removed from service.
made from one side This was verified through only. Incorporate inspection. In addition this in the DRQR App. station ~ procedures II. preclude the use of this type head.
2.1.3.14 2-18 4.10.4.3 Use ASME Section V, OPCo. considers the Article 7,_and ASME inspection methods and SA-613 Section 19 and acceptance criteria used 20 for acceptance currently to be criteria. completely adequate.
2.1.3.16 2-19 4.13.4.2 Mo'nitor any engine DPCo. has no known engine base cracks at base cracking. The bases alternate refueling on all engines have been outages. inspected for degraded microstructure and for the existence of cracks.
The DRQR App. II Rev. 2 includes periodic inspec-tion of the engine base.
2.1.3.16 2-19 4.13.4.2 Check all engine The bases for all CNS bases for degenerate engines have been l checked for proper micro-Widmannstatten i microstructure. structure. CNS 2 engines have proper structure.
CNS 1 engines have been i checked and are being i evaluated. Any degraded microstructure will be addressed in accordance with the SER paragraph 2.1.3.16.
CWH:09:05:86:B3
Page 11 NRC Question No. 8 Continued SER SER PNL Section Pg. # Section SER Recommendation DPCo Response 2.1.3.17 2-19 4.14.42 Fabricate fuel lines DPCo. uses 1008 steel from 1010 steel vice tubes supplied by TDI.
1008. Use shrouded These tubes are pre-fuel lines. service tested using eddy current. OPCo. has had no failures of injection tubing and feels that the currently supplied tubing is adequate.
2.1.3.14 2-2 4.14.4.2 Installation of tubing OPCo. has included should include specific instructions for specific instructions tightening fuel injection for fittings. tubing fittings in the maintenance procedures.
2.1.3.14 2-20 4.14.4.2 Check fuel tubing The OG M&S App. II fittings for signs of includes this recommenda-leakage after each tion to be carried out on shutdown. a monthly basis. In addition App. II Section A, Table 1 includes a provision' to check the engine for leaks on an hourly basis.
l 2.2.3.22 2-21 4.17.4.3 R.T. friction welded DPCo. will follow OG
! push rods. Destruc- recommendation to P.T.
! tively test period- all push rods. Based
! ically a friction on this inspection and welded push rod, the satisfactory perfor-mance of the friction welded design the PNL recommendations will not be performed.
2.1.3.24 2-22 4.19.4.3 Implement full lubri- Based on the performance cation of turbo's of the turbos with the during coast-down. modified pre and post L.O. system DPCo. does not l
feel the PNL recommenda-tion is justified. The turbo performance will continue to be evaluated.
If degradation is noted this recommendation can be reconsidered.
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Page 12 NRC Question No. 8 Continued SER SER PNL Section Pg. # Section SER Recommendation DPCo Response 2.1.3.24 2-22 4.19.4.3 Spectrographic and. DPCo. will conduct these ferrographic analysis analyses on a quarterly should be conducted basis, on a quarterly basis.
2.2 2-24 None Recommendations from See NRC Question 9.
detailed review by PNL in PNL 5444, 10 components.
2.2 2-24 None Implement all 0/G DPCo. has implemented all Phase II recommenda- recommendations with the tions, exception of those noted in References 5, 6, 7, 8 and 9.
- 9. NRC Question:
Provide a response to the plant specific items noted in Section 2.2 of the SER.
DPCo. Response:
Component Part No. PNL-5444 Recom/Sug. DPCo. Response Intercooler F-068 Monitor Air Temp. and A trend analysis is air and waterside AP included in App. II for trend analysis. of the DRQR to monitor intercooler performance.
Main Bearing Shells 02-310D NRC confirmation No action required review of Failure on DPCo's part.
Analysis Associates Review of OG component discrepancies.
Cam Shaft - 02-350C Redesign to eliminate No problems assoc.
supports, bolting the.use of cotter pins. with the use of cotter pins has been seen. DPCo. proce-dures and DRQR App.
II cover the roper installation of cotter pins. DPCo.
feels that the current design is adequate.
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Page 13 NRC Question No. 9 Continued Component Part No. PNL-5444 Recom/Sug. DpCo. Response Idler Gear 02-355B Redesign to eliminate Same as 02-350C Assembly cotter pins.
Intake and exhaust 02-360B Replace valves if This recommendation valves flaking or loss of is included in DPCo.
chrome plating is procedures.
_present.
Air Intake Manifold 02-375 Further incidence of The station has cracking should be procedures in place investigated thoroughly. which would require full investigation of such cracking.
Intake / Intermediate 02-390A/B Inspect rocker boxes at This inspection is and exhaust rocker the rocker shaft bolts included in DRQR shaft assemblies. during RFO's. App. II, component 02-362A at overhaul.
A TDI SIM has been ,
issued which addresses the potential for crack-ing in this area.
Intercooler Pipe 02-436A If a seismic event In the event of an Coupling exceeding the Site event exceeding 1/2 Seismic Limits occurs, SSE then this system inspect and evaluate would be inspected, couplings. evaluated, and reported to the NRC in accordance with 10CFR, Part 100,
- Appendix A, l Paragraph V.(a)(2).
Misc. Equipment- 02-810E Record jacket water Jacket water Jacket Water Stand temperatures daily temperatures are Pipe Heater and trend monthly recorded daily dur-excursions above ing engine standby set-point. and hourly during operation. These logs are reviewed by f personnel responsi-ble for engine performance.
Oil Pre-lube Filter 02-820E Maintain records and DRQR Appendix II trend AP versus time. includes this recommendation.
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Page 14
- 10. NRC Question:
What is DPCo's response to any Part 21 item received after Dec.19857 How does DPCo keep abreast of significant events occurring on TDI engines at other plants. A review of the LER's associated with .the TDI's engine received since the generic SER was drafted (Dec. 1985) was requested.
DPCo. Response:
Only one Part 21 item has been received since Dec.1985. (10CFR Part 21 No.
136, dated July 2,1986 and follow up letter dated Aug. 13,1986). This item is addressed below:
10CFR21 notification by TDI (July 2,1986) concerned a potential problem with the fastening of the engine's connection rod assembly.
The TDI investigation revealed that the connecting rod cracking was caused by insufficient clamping force applied through the rod bolting. Torque methods were used to apply fastener preload. Galling between the washer surface and the bolt head reduced the amount of torque that was converted preload.
Duke Power Company procedures for con rod- bolt installation -include determining preload with Raymond Bolt Gauge ultrasonic equipment. With this method, the desired preload is achieved regardless of galling or other frictional losses.
All Catawba con rod bolts have been installed using this method.
The nickel plated washers, recommended by TDI's August 13, 1986 letter, will be installed as the con rods are disassembled for inspection or repair.
We therefore conclude that this problem will not occur at Catawba and no further action will be necessary beyond those described in o^ur preventative maintenance program.
With respect to LER's the following is submitted:
i The staff also requested that Duke Power review any LER's which concerned TDI diesel generators, that were reported since the Staff's generic SER was drafted i in December 1985. Duke Power does not receive copies of LER's from other licensees with TDI diesel generators. Furthermore, diesel failures would be reported. to the NRC by way of Special Reports (Technical Specification 6.9.2) and not in LER's.
s Information on problems with diesel generators is received from a variety of i sources, including:
- 1. Part 21 reports (vendor).
- 2. IE Bulletins, IE Information Notices, and Generic Letters (NRC). IEIN l 86-73 dated August 20, 1986 advised the industry of recent diesel i generator problems.
- 3. NRC/INPO Daily Status Report (INPO).
- 4. Nuclear Network (INPO).
- 5. NPRDS (INPO).
- 6. NOMIS (NUS).
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Page 15 Question No. 10 Continued Through these sources and personal contacts with counterparts at other utili-ties, we feel that we are well informed as to significant problems with TDI or other vendor diesel generators.
- 11. NRC Question:
Address Catawba's program for investigating the root cause of D/G failures such as the recent problems with the fuel racks at Catawba Unit 2.
DPCo Response:
As discussed in the Special Report submitted to NRC/ Region II on August 7, 1986, failures number three through eight on D/G 2A were attributed to bi, ding of the fuel racks. A description of each failure, the corrective action and the successful retest of D/G 2A were documented in a Special Report to the NRC.
Following each failure, actions deemed appropriate to resolve the problem were taken. The 2A D/G was later declared operable based on the successful comple-tion of a re-test. Therefore there was no reason to believe that corrective actions were inappropriate or inadequate.
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