Forwards Partial Response to NRC Compliance Bulletin 87-002, Fastener Testing to Determine Conformance W/Applicable Matl Specs, Including Procurement & Receipt Insp Program & Methods for Choosing Fasteners to Be TestedML20149F416 |
Person / Time |
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Site: |
Oconee, Catawba, McGuire, University of California - Irvine, 05000000 |
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Issue date: |
01/12/1988 |
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From: |
Tucker H DUKE POWER CO. |
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To: |
Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
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References |
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IEB-07-002, IEB-7-2, IEB-87-002, IEB-87-2, NUDOCS 8801140236 |
Download: ML20149F416 (12) |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H5811999-10-15015 October 1999 Forwards 1999 Update to FSAR, for McGuire Nuclear Station.With Instructions,List of Effective Pages for Tables & List of Effective Pages for Figures ML20217F3261999-10-13013 October 1999 Submits Quantity of Tubes Insp from Either Side of SGs A-D & Lists Tubes with Imperfections,Locations & Size.No Tubes Removed from Svc by Plugging.Total of Eleven Tubing Wear Indications Identified at Secondary Side Supports in SGs ML20217F3591999-10-13013 October 1999 Forwards Info Copy of Cycle 14 COLR for McGuire Nuclear Station,Unit 1 ML20217F8011999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of McGuire Nuclear Station.Areas That Warranted More than Core Insp Program Over Next Five Months,Not Identified.Historical Listing of Plant Issues Encl ML20217G7861999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20217F8231999-10-13013 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 ML20217J5091999-10-0606 October 1999 Forwards Revs to Section 16.15-4.8.1.1.2.g of McGuire Selected Licensee Commitments Manual.Section Has Been Revised to Allow Testing of Portions of DG Fuel Oil Sys Every 10 Yrs ML20217C8351999-10-0505 October 1999 Communicates Correction to Info Provided During 990917 Meeting with Duke Energy & NRC Region Ii.Occupational Radiation Safety Performance Indicator Values Should Have Been Presented as 1 Instead of 0 ML20217C4471999-10-0404 October 1999 Forwards Insp Repts 50-369/99-06 & 50-370/99-06 on 990801- 0911.Determined That One Violation Occurred & Being Treated as Non-Cited Violation ML20212J2191999-10-0404 October 1999 Informs That Util 980326 Response to GL 97-06, Degradation of SG Internals Provides Reasonable Assurance That Condition of Steam Generator Internals Are in Compliance with Current Licensing Bases for Facility ML20212J7801999-10-0404 October 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for McGuire NPP & 990615.Informs That NRC Reviewed Responses & Concluded That All Requested Info Re Y2K Readiness Provided.Subj GL Considers to Be Closed ML20217K2651999-10-0101 October 1999 Forwards Retake Exams Repts 50-413/99-302 & 50-414/99-302 on 990921-23.Two of Three ROs & One SRO Who Received Administrative Section of Exam Passed Retake Exam, Representing 75 Percent Pass Rate ML20212J3011999-10-0101 October 1999 Forwards Exemption from Certain Requirements of 10CFR54.17(c) Re Schedule for Submitting Application for Operating License Renewal.Se Also Encl 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 ML20212M1651999-09-23023 September 1999 Refers to 990917 Meeting at Region II Office Re Licensee Presentation of self-assessment of McGuire Nuclear Station Performance.List of Attendees & Licensee Presentation Handouts,Encl 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 ML20212D1671999-09-20020 September 1999 Forwards Exemption & SER from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Re Isolation of Main Steam Branch Lines Penetrating Containment.Exemption Related to Licensee Application ML20212B6491999-09-15015 September 1999 Informs That Encl Announcement Re 990913 Application for Amend to Licenses NPF-9 & NPF-7 Forwarded to C Observer in North Carolina,For Publication 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 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 ML20212B4641999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for Catawba Nuclear Station,Units 1 & 2 ML20216E8791999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for July 1999 for McGuire Nuclear Station 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 ML20212A0501999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementing Code Case for Duration of Insp Interval ML20212A2631999-09-0909 September 1999 Forwards Rev 25 to McGuire Nuclear Station,Units 1 & 2 Pump & Valve Inservice Testing Program, IAW 10CFR50.55a. Section 8.0 Contains Summary of Changes & Detailed Description of Changes Associated with Rev 25 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 ML20211J3671999-08-31031 August 1999 Forwards Public Notice of Application for Amend to License NPF-9 Seeking one-time Extension of Surveillance Frequency for TS SR 3.1.4.2 Beyond 25% Extension Allowed by TS SR 3.0.2 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 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 ML20211K8831999-08-26026 August 1999 Forwards Insp Repts 50-369/99-05 & 50-370/99-05 on 990620-0731.Two Violations Occurred & Being Treated as NCVs 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 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 ML20211G5181999-08-24024 August 1999 Forwards SE Re second-10-yr Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 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 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 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 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 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217H5811999-10-15015 October 1999 Forwards 1999 Update to FSAR, for McGuire Nuclear Station.With Instructions,List of Effective Pages for Tables & List of Effective Pages for Figures ML20217H0041999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217F3261999-10-13013 October 1999 Submits Quantity of Tubes Insp from Either Side of SGs A-D & Lists Tubes with Imperfections,Locations & Size.No Tubes Removed from Svc by Plugging.Total of Eleven Tubing Wear Indications Identified at Secondary Side Supports in SGs ML20217F3591999-10-13013 October 1999 Forwards Info Copy of Cycle 14 COLR for McGuire Nuclear Station,Unit 1 ML20217G7861999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for McGuire Nuclear Station,Unit 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 ML20217J5091999-10-0606 October 1999 Forwards Revs to Section 16.15-4.8.1.1.2.g of McGuire Selected Licensee Commitments Manual.Section Has Been Revised to Allow Testing of Portions of DG Fuel Oil Sys Every 10 Yrs ML20217C8351999-10-0505 October 1999 Communicates Correction to Info Provided During 990917 Meeting with Duke Energy & NRC Region Ii.Occupational Radiation Safety Performance Indicator Values Should Have Been Presented as 1 Instead of 0 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-1999-004, 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 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 ML20216E8791999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for July 1999 for McGuire Nuclear Station ML20212A2631999-09-0909 September 1999 Forwards Rev 25 to McGuire Nuclear Station,Units 1 & 2 Pump & Valve Inservice Testing Program, IAW 10CFR50.55a. Section 8.0 Contains Summary of Changes & Detailed Description of Changes Associated with Rev 25 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 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 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 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 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 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 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 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 ML20210S2231999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl 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 ML20210R0031999-08-10010 August 1999 Forwards Revised TS Bases Pages to NRC for Info & Use. Editorial Changes Were Made to Correct Incorrect UFSAR Ref Number Associated with Certain Reactor Coolant Sys Pressure Isolation Valves ML20210T4511999-08-10010 August 1999 Forwards Response to NRC RAI Re 981014 Standby Nuclear Svc Water Pond Dam Audit Conducted by FERC ML20210R4311999-08-10010 August 1999 Forwards Summary Rept of Mods,Minor Mods,Procedure Changes & Other Misc Changes Per 10CFR0.59 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 ML20209H6921999-07-15015 July 1999 Forwards Comments on Preliminary Accident Sequence Precursor Analysis Provided in NRC Re Operational Condition Reported in LER 269/1998-04 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 ML20209H1551999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for May 1999 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 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 ML20209G5151999-07-0808 July 1999 Forwards Amended Pages to Annual Radioactive Effluent Release Repts, for 1997 & 1998 for McGuire Nuclear Station. Portion of Rept Was Inadvertently Omitted Due to Administrative Error,Which Has Been Corrected ML20196G3721999-06-24024 June 1999 Documents Verbal Info Provided to NRR During Conference Call Re Relief Requests 98-002 & 98-003 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 ML20195K3601999-06-14014 June 1999 Forwards MORs for May 1999 for McGuire Nuclear Station,Units 1 & 2 & Revised MORs for Apr 1999.Line 6 Max Dependable Capacity (Gross Mwe) on Operating Data Rept Should Be Revised to 1114 from Jan 1998 to Apr 1999 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) 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L0101990-09-19019 September 1990 Provides Addl Response to Violations Noted in Insp Repts 50-369/90-11 & 50-370/90-11,per .Corrective Action:Operations & Compliance Mgt Further Examined Event & Concluded That Trains Vc/Yc Inoperable Per Special Order ML20059L0091990-09-18018 September 1990 Informs of Delay in Response to Violations Noted in Insp Repts 50-369/90-14 & 50-370/90-14.Delay Due to Ongoing Review ML20059J7121990-09-14014 September 1990 Forwards Monthly Operating Rept for Aug 1990 for McGuire Nuclear Station Units 1 & 2 & Monthly Operating Status Rept for Jul 1990 ML20059L5491990-09-14014 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 ML20065D4671990-09-11011 September 1990 Informs of Delay in Response to Violation Noted in Insp Repts 50-369/90-11 & 50-370/90-11,per Commitment in ML20064A8031990-09-10010 September 1990 Responds to NRC Ltr Re Violations Noted in Insp Repts 50-369/90-13 & 50-370/90-13.Corrective Actions:Procedures Dealing W/Fuel Handling Will Be Enhanced by Adding Sign Off to Sections Which Ref Fuel Handling in Tech Specs 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) 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 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) ML20064A5671990-09-0101 September 1990 Advises That Corrective Actions Re Violation of Insp Rept 50-369/89-01 & 50-370/89-01 Will Be Completed by 910101 ML20059D3461990-08-30030 August 1990 Forwards Semiannual Effluent Release Rept for First Half of CY90 & Revs to Process Control Program 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 ML20059D1901990-08-22022 August 1990 Responds to Violations Noted in Insp Repts 50-369/90-11 & 50-370/90-11.Corrective Actions:Valves VC-1,VC-2,VC-3,VC-4, VC-9,VC-10,VC-11 & VC-12 Reopened Upon Discovery of VC-1 - VC-4 Being Closed & Procedure IP/0/13/3006/09 Revised ML20059G9141990-08-22022 August 1990 Forwards Public Version of Revised Epips,Including Change 0 to RP/O/A/5700/01,Change 0 to RP/O/A/5700/02 & Change 0 to RP/O/A/5700/03 ML20059B4451990-08-20020 August 1990 Requests That NRC Approval of Original Relief Request 89-02 Be Extended to Include Changes to Mods MG-22233 & MG-22243 as Described.Hydrostatic Testing Impractical Due to Inadequacy of Test Boundaries 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 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 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 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 ML20063Q0951990-08-15015 August 1990 Forwards Monthly Operating Rept for Jul 1990 for Catawba Nuclear Station Units 1 & 2 & Revised Rept for June 1990 ML20063Q0901990-08-15015 August 1990 Forwards Monthly Operating Repts for Jul 1990 for McGuire Nuclear Station Units 1 & 2 & Revised Rept for June 1990 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 ML20063Q0181990-08-0707 August 1990 Confirms That Planned Corrective Actions Listed in Paragraph 3 of Insp Repts 50-369/90-10 & 50-370/90-10,appropriately Described ML20056A9541990-08-0101 August 1990 Provides Final Response to NUREG-0737,Item II.D.1, Performance Testing of Safety Relief Valves. Util Will Change Seal Configuration for Existing Valves to Seal on Steam Medium & Install Continuous Drain for Loop Piping ML20058L1811990-08-0101 August 1990 Forwards Safety Evaluation of Large Break LOCA Event Reanalysis Per 10CFR50.46 Re Peak Clad Temp Increases ML20058L4061990-08-0101 August 1990 Forwards Rev 0 to Inservice Insp Rept Unit 1 McGuire 1990 Refueling Outage 6 ML20059K0291990-08-0101 August 1990 Forwards Comments on Reactor Operator & Senior Reactor Operator Written Exams Administered on 900730 ML20058P3261990-08-0101 August 1990 Forwards Public Version of Rev 26 to Station Directive 3.8.4, Onsite Emergency Organization 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 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 ML20056A1571990-07-23023 July 1990 Forwards Public Version of Change 0 to RP/0/A/5700/10 & Rev 25 to Section 18.2 of Radiation Protection Manual.W/ Dh Grimsley 900730 Release Memo 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 NLS9000259, Responds to Violations Noted in Insp Repts 50-369/90-09 & 50-370/90-09.Corrective actions:in-house Training Will Be Provided on Correct Method for Determining Proper Response to Problem Investigation Processes1990-07-16016 July 1990 Responds to Violations Noted in Insp Repts 50-369/90-09 & 50-370/90-09.Corrective actions:in-house Training Will Be Provided on Correct Method for Determining Proper Response to Problem Investigation Processes 1990-09-05
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.- DUKE POWER COMPANY P.O. BOX 33180 CHAMLOTTP, N.C. 28242 HAI. B. TUCKER retmenoMn m reussen (yo4) aya-4 sag January 12, 1988 Dr. J. Nelson Grace Regional Administrator U.S. Nuclear Regulatory Commission ,
Region II 101 Marietta Street, NW Suite 2900 Atlanta, Georgia 30323
Subject:
Duke Power Company Oconee Nuclear Station Docket Nos. 50-269, - 270, - 287 McGuire Nuclear Station Docket Nos. 50-369, -370 Catawba Nuclear Station '
Docket Nos. 50-413, -414 Response to NRC Compliance Bulletin No. 87-02 Attached is a partial Duke Power response to NRC Compliance Bulletin No. 87-02, "Fastener Testing to Determine Conformance with Applicable Material Specifications." Included as attachments to this letter is the following information required by the bulletin.
Attachment A Description of the Duke Power Procurement and Receipt Inspection Program for Fasteners Attachment B Description of the Duke Power Controls Used During Storage and Issuance From Stock to Assure the Appropriate Use of Fasteners Attachment C Method for choosing the Fasteners to be Tested Attachment D Status and Schedule of the Evaluation of Fastener Testing Results I
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'8801140236 880112 PDR ADOCK 05000269 0 .DCD
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Dr. J. Nelson Grace Page #2 January 12, 1988 At this time, we are unable to submit the test results and the evaluation thereof. This is because 1) we were unable to complete the overall workload required by this bulletin within the 60-day time allotment; 2) the time required to interface with vendor testing laboratories; and 3) the performance of Charpy Impact Testing on some samples. This latter item, although not specifically required by Compliance Bulletin 87-02, was requested by the NRC Resident Inspectors based upon interpretation of the NRC Temporary Instruction 2500/26 covering the bulletin.
Presently we have completed the mechanical and chemical testing of all samples (except the additional impact testing of the required samples). The status and schedule of the evaluation of the test reaults is detailed in Attacament D.
I declare under penalty of perjury that the statements set forth herein are true and correct to the best of my knowledge.
Very truly yours, b/kr Hal B. Tucker HBT/JSW/lec Original Letter and Copy of Attachments:
U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 xc: (w/ Attachments):
NRC Resident Inspector l Oconee Nuclear Station NRC Resident Inspector McGuire Nuclear Station NRC Resident Inspection Catawba Nuclear Station 1 I I
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Attachment A Duke Powr r Company Response to NRC Compliance Bulletin 8 7-02 "Description of the Duke Power Procurement I and Receipt Inspection Program for Fasteners" l j INTRODUCTION The Quality Assurance Procurement Program is based on the following: I a) Review of requisitions and purchase orders by QA personnel b) QA Vendor audits and surveillances of suppliers c) Duke QA releases required prior to shipment d) Review of vendor documentation by QA Vendors e) Receiving inspection by site QA QA REVIEW OF REQUISITIONS AND PURCHASE ORDERS l
All QA Condition purchase orders and requisitions are reviewed by Quality Assurance personnel to assure the appropriate documentation requirements are specified on the purchase orders.
QA VENDOR AUDITS AND SURVEILLANCES During audit / surveillance activities, Duke representatives verify that the vendor has applied applicable sections of their approved quality program to the materials being purchased. examples of audit and surveillance activities are a) Reviewing Certified Material Test Reports (CMTR's);
comparison to ASME Code Section II requirements as applicable.
b) Reviewing heat treat records.
c) Performing dimensional verification.
d) Reviewing audit reports, inspection reports, Nondestructive Examination (NDE) reports, equipment calibration records, and employee qualifications and certification records, ei verifying proper markings.
f) Reviewing the vendor's purchase documents.
g) Verifying that stock materials used were from approved source or (when applicable) properly qualified (eg. , NCA-3 86 7. 4 e) .
h) Verifying acceptance of physical properties such as hardness, tensile, yield, and impact through document review, i) Witnessing manufacturing and testing processes.
4 Attachment A Response To NRC Compliance Bulletin 87-02 Page 2 QA RELEASE BY QA VENDORS In addition to subject audits and surveillances, the vendor is required by each safety related purchase order to receive a Duke QA release prior to shipment, except as exempted per procedure.
When notified by the vendor that an item is ready for shipment, QA Vendors schedules a visit to the vendor or grants a telephone release. We perform surveillances for approximately 10% of the purchase orders. For the other 90%, QA Vendors perform telephone communications to obtain the suf ficient information to grant releases. The QA Vendors Division documents their release on Form QA-605, "QA Vendors Release". Verification of proper marking, proper documentation, and material manufacturer would be addressed as a minimum.
QA REVIEW OF VENDOR DOCUMENTATION Vendor documentation is forwarded to Duke's QA Vendor Division Documentation Section for review. If found acceptable, documentation is approved and forwarded to applicable etations (approval is required and forwarded to applicable stations use) .
The applicable site is notified if problems are noted and material is placed in "HOLD" statues pending satisfactory resolution.
During the review, the following areas are verified:
a) Comparisons to purchase order.
b) Chemical and physical properties reported are compared with applicable material specifications.
c) Assure applicable ASME Code requirements have been included ,
in the certification.
d) Necessary historical and added testing data are included in the documentation package for material qualified per i NCA-3 86 7. 4 (e) .
e) Verify that the material supplier is an approved vendor, l
QA RECEIVING INSPECTION The receiving inspections at Duke's Nuclear sites are performed to I ensure conformance of material to the purchase order. The QA l procedure used for receipt at the site requires the material to be !'
visually examined to assure identification and markings are in accordance with the purchase orders, standards and the vendor )
4 documentation. ;
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Attachm2nt A f
Response To NRC Compliance Bulletin 87-02 Page 3 QA RECEIVING INSPECTION CONTINUED:
All QA condition materials are identified with an unique OA Tag Number in addition to the assigned company number (i.e., MMIS Number). The QA Tag Number is specified to a given purchase order and a single line on that purchase order. This tag is either attached to the item)s .itself or on the packages (s) or container (s). Some items transferred from a Construction Program may not be traceable to purchase orders. In those cases sufficient documentation shall be specified to establish the acceptability of the item.
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-Attachment B Duke power Company ;
Response to NRC Compliance Bulletin 87-02 "Description of the Duke Power Controls Used During Storage and Issuance From Stock to Assure the Appropriate Use of Fastener" L
All fasteners are stored in accordance with the requirements of ANSI N45.2.2 Level B or C. procedures in each station's materials manual describe the controls applied for the handling and storage of items (not just fasteners).
Stock fasteners are assigned a company number which facilitates in the retrieval of procurement information in addition to being used in the control of inventories and other company business needs. Non-stock fasteners are not identified by a company number since, in most situations, they are fasteners that are not cornen to other uses or applications.
Fasteners are identified for use normally in one of two ways. First, the Duke Design Engineering Department's piping installation specification (covering flange connections, etc.), hanger installation specification, and various electrical installation specifications are all used in identifying a need for fasteners. The second and most often used method is through each equipment specification and associated instruction manuals, maintenance manuals, and equipment drawings which have bills of material. The majority of fasteners in '
this category would be identified by a manufacturer's part number or by some relationship to the equipment. Much of the information from these documents can ,
be found on data bases. After selection for procurement through one of the methods above, the fastener would be stored and identified as described previously. ,
In addition to the assigned company number, all stock and non-stock QA fasteners are assigned a unique QA tag number. This number is unique to a specific line item on a specific purchase order. For safety-related fasteners, the QA tag number facilitates traceability to the installed location required by 10 CFR 50 Appendix B. The issuance of QA fasteners is controlled by procedures found in each station's materials manual. These fasteners are issued to a work request, which is the Duke administrative program used to control maintenance work '
activities at each station, that identifies and captures all pertinent data such as company and QA tag number, quantities, procedures utilized, and other descriptive information. Although non-QA fasteners are not required to be issued !
to a work request, in many cases they will be included since the equipment they are used or. is safety-related. Their actual function in those cases, however is not considered safety-related. If fasteners have not been adequately identified l on design documents or data bases and there is a question concerning the proper ;
fastener, it is the responsibility of the site engineering section to provide (with the help of Design Engineering if needed) the maintenance technician with the correct fastener for that particular application.
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Attachment C l
Duke Power Company Response to NRC Bulletin 87-02 Method for Choosina the Fasteners to be Tested.
The selection process began by listing all: 1. Bolts 2. Scraws 3. Studs 4.
Capscrews and 5. Nuts described in the KMIS (Materials Management Information System) computer data files for each station.
l The following factors were used in the selection of test samples.
- 1. Fasteners listed as standard issue fasteners, not necessarily listed as a part for a specific component, were chosen. In a few cases (especially Oconee), there was not a suitably large selection of general issue fasteners and so the list was supplemented by equipment vendor supplied fasteners.
- 2. Fasteners that represented an assortment of different materials were chosen. For a reasonable number of fasteners, the description listed the material type.
- 3. Fasteners that represented an assortment of manufacturers and suppliers were chosen. The MMIS list had very little information on manufacturers and suppliers but the samples chosen took this requirement into account as much as possible.
- 4. If tensile tests were required (such as safety related bolts), fasteners had to be at least 4 inches long and, if possible, with either 3/8-16 or 3/4-10 threads to accommodate tensile specimen fabrication. To support chemical analysis, the fasteners were at least 3/8 inch nominal size. In some cases, samples were slightly smaller than this. To assure their representation, some safety related fasteners shorter than 4 inches were added to the Non-Safety list. (Testing under bulletin 87-02 is identical for QA and non-QA bolts except for tensile testing.)
A list of forty fasteners was made for each station and presented to each station's NRC resident inspector as a draft from which to begin. The MMIS numbers that begin with "1007", the Construction Department numbering method, are coded for the piping class they are to be used or.. For safety related fasteners the last alpha character is either A, B, or C. The eight or nine digit numbers, Nuclear Production Department numbering method, are safety related if they end with an "N". Non safety related fastener lists contain a number of safety related fasteners because of the reason stated in paragraph 4.
above and because general purpose fasteners are often purchased as safety related to allow a greater versatility of application. Some minor discrepancies were found in the nomenclature of MMIS descriptions. A final i list of fasteners from each station is attached.
McGuire Fastener Sampling On November 25, 1987 Bill orders, NRC Resident Inspector for McGuire, reviewed the list of fasteners and performed an inspection of the fasteners in stock.
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Attachment C The NRC Temporary Instructions concerning this bulletin recommended fasteners be added if they had one of nine manufacturer codes or no code. Four examples of this were found and two of them were exchanged with others on the list.
Also found during the inspection was threaded rod which is often issued for making studs. A sample of this was added also. Mr. Orders then reviewed the diversity of materials and manufacturers and agreed that the adjusted sample selection was acceptable. Six samples were replaced on Decemb3r 2, 1987 because the samples originally chosen were out of stock or daleted from stock.
A letter was written to document this adjustment to the line. Other minor list adjustments were made after verbal confirmation with Bill Orders.
For HMIS sequence number 0253580, Sample Numbers MNS/NQ/SCRW/15 and 16, two different manufacturers were found so both were used.
Catawba Fastener Sampling On November 30, 1987 Mark Lesser, NRC Resident Inspector for Catawba, reviewed the list of fasteners, tabulated them by material type, and performed an inspection of the fasteners in stock. Threaded rod was found but not chosen because a storekeeper familiar with fasteners atated that it was not issued very often; also the material types and manufacturers were represented by other bolt samples. Two non-QA bolt samples were chosen and one of them was added to the list. Mr. Lesser then reviewed the diversity of materials and manufacturers and agreed that the adjusted sample selection was acceptable.
Four fasteners were replaced on December 3, 1987 because the samples originally chosen were out of stock or were misnumbered. A letter was written to document this adjustment to the list.
Oconee Fastener Sampling On December 1, 1987 Len Wert NRC Resident Inspector for Oconee and Nick Economos of Region II reviewed the list of fasteners, tabulated them by material type, and performed an inspection of the fasteners in stock. Threaded rod was found and an example was added to the list. Silica Bronze and eye bolt fasteners were removed from the list because they were not of interest to this bulletin. Oconee carries very few standard issue, general purpose fasteners and so most of the fasteners selected were Safety Related and associated with a specific plant purpose. Two materials and manufacturers of nuts were found under MMIS number 1007B3ANIC0B010 and so both were used (samples GNS/QA/ NUT /26 and 27). MMIS number 23210244N was received as a nut and bolt pair so the bolt is sample ONS/QA/ BOLT /5 and the nut is ONS/QA/ NUT /22. Mr. Economos and Mr. Wert both reviewed the diversity of materials and manufacturers and agreed that the adjusted sample selection was acceptable. Len Wert later notified us that MMIS number 1007B1ASICOG007050 was not a Safety Related fastener and it was exchanged for a QA fastener from the non-QA list.
Sample Testing Chemical analysis for all fastener samples was performed by Chicago Spectro Service Laboratory Inc. 4848 South Kedzie Ave. Chicago IL 60632. This company i is an app.oved vendor for providing analytical services under the Duke Power QA l program. Hardness and tensile testing was performed in and under the QA program of the metallurgy laboratory of the Production Support Department of Duke Power Company. It has been proposed that Law Engineering Servic e !
Charlotte NC perform the Charpy impact property tests. Law Engineering alp l has Duke QA approval for material testing. !
Attachment C Oconee List of Fastener Samples (As of January 5, 1988)
Safety Related Bolts Sample Number MMIS Description MMIS Number ONS/QA/ BOLT /1 Bolt Mach Hex SS 3/4-10X3 1/2 SA-193/B8 02624012N ONS/QA/ BOLT /2 Bolt, Mach Hex HD SS 5/8-11X6 SA193/B8 02624017N ONS/QA/ BOLT /3 Bolt, Mach HVY KD CS 7/8-9 X 6-1/2 A325 02623399N ONS/QA/ ROD /4 Rod,THRD Alloy Steel 3/4-10 SA193 GR B7 1007B1ARICOB006 ONS/QA/ BOLT /5 Bolt, Hex Head RV 1-8X3 1/2 193 B7 23210244N ONS/QA/ STUD /6 Stud,CS 112T 1-8X7-1/4 OTSG PRI INSPECT 23240157N ONS/QA/ STUD /7 Stud, Load Pipe Clamp .750 X 10UNCX6.50 0298EE04FN ONS/QA/ STUD /8 Stud 1006688-001 MK#145 3/4" OTSG SEC 02691449N ONS/QA/ CAP /9 Capscrew, Hex HD 1-1/8-7X8 1/4 CD SA193 02653107N ONS/QA/ CAP /10 Capscrew, Soc HD 1-1/2-6X4 A574 LIMITOR 02655186N Non Safety Bolts ONS/NQ/ BOLT /11 Bolt Machine Hex HD CS 7/8-9 X 4 GR 8 02623157 ONS/NQ/ BOLT /12 Bolt Mach HVY Hex HD CS 1/2-13 X 2 A325 02621252N ONS/NQ/ BOLT /13 Bolt, Bracket 8348556 Diesel Generator 29020732N ONS/NQ/ STUD /14 Stud,B7 CL G 7/8-9 5 SA193 1007B1ASIC0G007050 ONS/NQ/ BOLT /15 Bolt, Hex HD 1 1/4 X 6 A325 RCP Motor 20110249 ONS/NQ/ BOLT /16 Bolt,Shell Mnwy Cvr 1-1/4-8 X 10 MSRH N205023453 ONS/NQ/ BOLT /17 Bolt,023 5/16 X 4 Fuel & Lube Oil Pmp 20391186N ONS/NQ/SCRW/18 Screw,Assy HH 1/2-13X2 306/307 10 KIP 0298Cv55FN ONS/NQ/SCRW/19 Screw, Cap Hex HD SS 3/8-16 X 2 B8M 02652100N ONS/NQ/ CAP /20 Capscrew, Soc HD 20 1X3-1/4 RCP Bingham 20110389N 1
Safety Related Nuts ONS/QA/ NUT /21 Nut, Hex AS 3/8-16 SA194 GR 8 CL B 1007CIAMICOB003 ONS/QA/ NUT /22 Nut, Hex 1-8 194 B7 CS (with bolt) 23210244N
. ONS/QA/ NUT /23 Nut, Hex CD 7/16-20 GRADE 8 02640007N ONS/QA/ NUT /24 Nut, Hex SS 3/8-16 A194 GRADE B8M 02642083N ONS/QA/ NUT /25 Nut,HVY Hex SS 3/4-10 SA194 GR 8 02642061N ONS/QA/ NUT /26 Nut. Hex 1-8 SA194 2H QA Tag 39323 Mfg"J" 1007B3ANICOB010 ONS/QA/ NUT /27 Nut, Hex 1-8 SA194 GR7 QA Tag 46009 Mfg"CU" 1007B3ANICOB010 ONS/QA/ NUT /28 Nut,HVY Hex CS 3/4-10 A563 GR A 02641784N ONS/QA/ NUT /29 Nut,HVY Hex CS 5/8-11 A325 GR A 02641237N ONS/QA/ NUT /30 Nut, Jam CS 2-3/4-4 A563 CL B 02641740N Non Safety Nuts ONS/NQ/ NUT /31 Nut.HVY Hex CS 1-1/8-7 A307 GR A 02641179N ONS/NQ/ NUT /32 Nut, Hex CS 1-3/8-6 SURE LOC 02641397 ONS/NQ/ NUT /33 Nut, Hex CS 2-4-1/2 2H SURE LOC 02641398 ONS/NQ/ NUT /34 Nut, Hex CS 7/8-9 GR8 02641864 ONS/NQ/ NUT /35 Nut.HVY Hex AS 3/4-10 A194 GR BM CL E 1007C5ANIC0E006 ONS/NQ/ NUT /36 Nut,HVY Hex CS 1-8 A307 GRADE A 02641211N l ONS/NQ/ NUT /37 Nut,HVY Hex CS 1 8 A325 GRADE A 02641210N ONS/NQ/ NUT /38 Nut,HVY Hex CS 1-8 A563 GRADE A 02641301N ONS/NQ/ NUT /39 Nut. Hex CS 1-1/4-8 SA194 GR 7 MOIST SEP N205023473 l ONS/NQ/ NUT /40 Nut,Manway 1006118-001 MK#160 OTSG SEC N232001153Q 1
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'* Attachment C
-4 Catawba List of Fastener Samples (As of December 11, 1987)
Safety Related Bolts Sample Number MMIS Description MMIS Number CNS/QA/ BOLT /1 Bolt, Machine Hex HD CS 3/8-16X5 A-307/A 02623970N CNS/QA/ BOLT /2 Bolt, Machine Hex HD CS 7/16-14X5 J429/5 02623903N CNS/QA/ BOLT /3 Bolt, Machine Hex HD CS 7/16-14X5 SA449 02623902N CNS/QA/ BOLT /4 Bolt, Machine HVY Hex HD Alloy 3/4-10X4 02624010N CNS/QA/ BOLT /5 Bolt, Machine HVY Hex HDCS 3/4-10X6 A325 02622100N CNS/QA/ BOLT /6 Bolt, Secondary Handholds S/G 1 1/4-8X5 23240072N CNS/QA/ STUD /7 Stud. Alloy Steel 3/4-10X6 SA193 GR B7 1007B1ASICOB006060 :
CNS/QA/SCRW/8 Screw, CAP 3/4-10X4 Camshaft Bearing Cap 29020956N 02653998N ;
CNS/QA/SCRW/9 Screw, Cap Hex HD CS 3/4-10X4 J429/8 CNS/QA/ STUD /10 Stud,Viv 3/4-10X5 3/4 ASME SA564 T630 244401851N ,
Non Safety Bolts ,
CNS/NQ/ BOLT /11 Bolt, Hex HD Silicon Bron 3/8-16X1 F468 02621207N CNS/NQ/SCRW/12 Screw, Cap Hex E CS 7/16-20X2 GR 2 02652451 i CNS/NQ/ BOLT /13 Bolt, Mach Hex HD CS 1 1/8-7X6 A193 GRB7 02622111 ,
CNS/NQ/ BOLT /14 Bolt, Machine W/ Nut Hex HD STL 5/16-18X2 02621014 ;
CNS/NQ/ BOLT /15 Bolt, Machine W/ Nut Hex HD STL 3/8-16X4 02621030 }
CNS/NQ/SCRW/16 Screw, Cap Hex HD SS 1/2-20X1 02654553 i CNS/NQ/SCRW/17 Screw, Cap Hex HD CS 7/16-20x4 GR2 02652453 l CNS/NQ/ BOLT /18 Bolt Lftng Lug Hex HD CS 1 1/2X6X14 A325 02624000 !
CNS/NQ/SCRW/19 Screw, Cap Soc HD STL 1/2-13X2 02651809 ;
i CNS/NQ/SCRW/20 Screw, Set SQ HD Alloy STL 1/2-13X3 02654488 ;
4 Safety Related Nuts i CNS/QA/ NUT /21 Nut,G1 Viv 6,3/4-10 SA194 GR 3M Borg W 244403773N !
CNS/QA/ NUT /22 Nut,HVY Hex 1 1/4-12X1 7/32X2 SA194/2H 02641775N !
CNS/QA/ NUT /23 Nut, Hex Alloy Stl 5/16-18 SA194 GR8 CL A 1007CIAMIC0A0005 :
CNS/QA/ NUT /24 Nut. Hex BR 5/16-18 X 1/4 X 1/2 02641923N l CNS/QA/ NUT /25 Nut Hex GT VLV 6&8,5/8-11 SA194 GRADE 8M 244103251N i CNS/QA/ NUT /26 Nut, Hex HD CS 5/8-11 X 9/16 X 15/16 02641915N l CNS/QA/ NUT /27 Nut.Special Hex 1 1/2-6 A563 GR B 02642095N CNS/QA/ NUT /28 Nut Hex SS 3/8-16 A194/B8 02641990N I
CNS/QA/ NUT /29 Nut, Hex Jam i 1/4-20 ASTM A194 GR 2H G 244102420N CSS /QA/ NUT /30 Nut. Hex Jam 3/4-10 ASTM A194 GR 8M CK V 235100925N Non Safety Nuts Nut,HVY Hex CS 3/4-10 SA194 GR 7 CL B 1007B3ANICOB006 !
CNS/NQ/ NUT /31 CNS/NQ/ NUT /32 Nut, Hex HVY STL 3/4-10X47/64X1 1/4 2B 02641027 f CNS/NQ/ NUT /33 Nut, Hex Silicon Bron 3/8-16X9/16X21/64 02641835 .
CNS/NQ/ NUT /34 Nut, Hex STL 7/8-14X3/4X1 5/16 ZN CH 02641011 !
CNS/NQ/ NUT /35 Nut.HVY Hex Alloy Stl 7/8-8 SA453 GR 660 1007BSAG1 LOA 013 !
CNS/NQ/ NUT /36 Nut.HVY Hex CS 1 1/4-8 SA194 GR 2H CL B 1007B2AN1 LOB 012 CNS/h0/ NUT /37 Nut.HVY Hex C3 1-8 A563/A 02641301N :
CNS/NQ/ NUT /38 Nut.HVY Hex CS 7/8-9 SA194 GR 2H CL B 1007B2AN1 COB 007 I CNS/NQ/ NUT /39 Nut. Hex CS 5/8-18 SA194/2H 02641764N CNS/NQ/ NUT /40 Nut Hax Manhole Cover D/G Engine 29021177N l l
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Attachment C 5-McGuire List of Fastener Samples (As of December 11, 1987)
Safety Related Bolts Sample Number KMIS Description MMIS Number t
MNS/QA/ BOLT /1 Bolt. Hex Head A-325 1 1/2-6X8 UNRC-2A 02622016N MNS/QA/ BOLT /2 Bolt Hex Head A-325 3/4-10X6 UNRC-2A 02621982N MNS/QA/ ROD /3 Rod, Threaded CS 3/4-10 SA193-B7 GR A 1007B1ARIC0A006 MNS/QA/ STUD /4 Stud,3/4-10XS SA193 GR B7 1007B1ASIC0A006050 MNS/QA/ STUD /5 Stud,3/4-10X5 1/4 SA193 GR B7 1007B1ASICOB006052 MNS/QA/ CAP /6 Capscrew, Hex Head 7/16-14X4 SA-193GR B7 02652967N MNS/QA/SCRW/7 Screw,CS Hex HD J429 Gr.8 1/2-13X3 1/2 02651885N 1 MNS/QA/SCRW/8 Screw,CS Hex HD 3/8-16X4 SA193 GR B7 02652950N MNS/QA/ BOLT /9 Bolt, Hex HD 1/2-13X7 3/4 SA307 GR A 1007A7ADIC0A004076 MNS/QA/ BOLT /10 Bolt, Hex HD 1/2-13X6 SA193 B8M 1007C9ADIC0A004060 Non Safety Bolts MNS/NQ/ BOLT /11 Bolt. Carriage Oval HD CS 3/8-16X6 02621512 MNS/NQ/SCRW/12 Screw Cap 1/2X8 UC 02654092 MNS/NQ/ BOLT /13 Bolt, Hex Head 1-8X4 A193 GR B7 For MSRs Non-Stock 5-L-1-1 MNS/NQ/ BOLT /14 Bolt. Machine CS Hex HD 1/2-13X4 A307/A 02623336 MNS/NQ/SCRW/15 Screw Cap 3/4X2 UC "Black Bethlehem Stl"02653580 MNS/NQ/SCRW/16 Screw Cap 3/4X2 UC "Plated KS Brand" 02653580 MNS/NQ/ BOLT /17 Bolt, Hex Head A-325 3/4-10X3 UNRC-2A 02621979N r MNS/NQ/ BOLT /18 Bolt, Hex 5/8-11X3 1/4 SA193 GR B8M 1007C9ADIC0A005032 MNS/NQ/SCRW/19 Screw, Cap 3/4X8 02655071 MNS/NQ/SCRW/20 Screw,CS Hex Head Cap 1/2-13X1 GR 5 02653189
, MNS/NQ/SCRW/21 Screw,CS Hex HD 3/4-10X4 1/2 A325 GR S 02653196 Safety Related Nuts MNS/QA/ NUT /22 Nut,3/4-10 SA194 GR B7 CLASS A 1007B3ANIC0A006 MNS/QA/ NUT /23 Nut.HVY Hex CS 3/4-8 A194 GR2H STRUCTRL 02641674N '
MNS/QA/ NUT /24 Nut, Hex 3/8-16 A307/A 02641513N MNS/QA/ NUT /25 Nut Hex 5/16-18 SA194 GR 2H CL B 02641748N MNS/QA/ NUT /26 Nut, Hexagon 7/16-14 ASTM A194 GR 8M 244102525N i
MNS/QA/ NUT /27 Nut, Hex CS 1/2-13X7/16X3/4 A307/A 02641512N MNS/QA/ NUT /28 Nut, Hex CS 1 1/2-8 A307 02641492N ,
MNS/QA/ NUT /29 Nut HVY Hex CS 3/4-10 SA194 GR 2H 1007B2ANIC0A006 MNS/QA/ NUT /30 Nut. Hex 1/2-13 SA563 GRADE A 1007C7AMIC0A004 MNS/QA/ NUT /31 Nut Cap CS 1/2-13 SA194 GR 2H CL A 1007B2AZ1C0A004 9
Non Safety Nuts ;
MNS/NQ/ NUT /32 Nut Hexagon 3/4 UNC 02641976 MNS/NQ/ NUT /33 Nut SS Hex 1/2-13 02641082 MNS/NQ/ NUT /34 Nut SS Hex 3/4-10 02641085 MNS/NQ/ NUT /35 Nut Hex Head,1/2-13X7/16 J429 GR8 02641076N '
MNS/NQ/ NUT /36 Nut Jam CS 3/8-16 A307 GR A STRUCTURAL 02641587N MNS/NQ/ NUT /37 Nut.20035 1-8UNC A582-GR416 P202635253 l MNS/NQ/ NUT /38 Nut, Hex 7/16-14 SA563 GR A 1007C7AMIC0A0007 :
HNS/NQ/ NUT /39 Nut, Hex 3/4-10 SA194 GRADE 8M 1007CSAM1C0A006 MNS/NQ/ NUT /40 Nut. Hex SS ANSI B18.6.3-1975 3/8-16 02641944N MNS/NQ/ NUT /41 Nut Cap CS 9/16-12 SA194 GR 2R CL A 1007B2AZ1C0A0009
Attachment D Duko Power Company Response to NRC Compliance Bulletin 87-02 "Status and Schedule of the Evaluation of Fastener Testing Results" The evaluation of fastener testing results is not complete as of January 12, 1988. Status of this effort is as follows:
- All samples have been selected and '
forwarded to the lab.
- All testing has been completed unless we determine that some of the samples require impact testing.
- We have completed the review of approximately 70% of the test results at this time.
- Up to this point, we have not discovered any significant deviation from the material specifications.
- Barring any significant findings, we j expect to complete our review, .
compilation, and submittal of the test l results by February 11, 1988.
- Any deviations requiring engineering or safety evaluation would extend this period.
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