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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 ML20217H0041999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for Catawba Nuclear Station,Units 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 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 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 ML20212E6471999-09-24024 September 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for Catawba NPP & 990615.Informs That NRC Reviewed Response for Catawba & Concluded That All Requested Info Provided.Considers GL 98-01 to Be Closed for Catawba ML20217A7911999-09-24024 September 1999 Forwards Insp Repts 50-413/99-05 & 50-414/99-05 on 990718- 0828 at Catawba Facility.Nine NCVs Identified Involving Inadequate Corrective Actions Associated with Degraded Svc Water Supply Piping to Auxiliary Feedwater Sys 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 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 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 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 ML20216E8791999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for July 1999 for McGuire Nuclear Station 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 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 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 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 ML20217G7861999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20217F3591999-10-13013 October 1999 Forwards Info Copy of Cycle 14 COLR for McGuire Nuclear Station,Unit 1 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 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 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 ML20216E8791999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for July 1999 for McGuire Nuclear Station ML20212B4641999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for Catawba Nuclear Station,Units 1 & 2 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 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 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 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 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 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 ML20210R4311999-08-10010 August 1999 Forwards Summary Rept of Mods,Minor Mods,Procedure Changes & Other Misc Changes Per 10CFR0.59 ML20210T4511999-08-10010 August 1999 Forwards Response to NRC RAI Re 981014 Standby Nuclear Svc Water Pond Dam Audit Conducted by FERC 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 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 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 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 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 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) ML20217G5771999-06-0909 June 1999 Forwards Post Exam Comments & Supporting Reference Matls for Written Exams Administered at Catawba Nuclear Station on 990603 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 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 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 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 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 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 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 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 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 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 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 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 ML20063Q0901990-08-15015 August 1990 Forwards Monthly Operating Repts for Jul 1990 for McGuire 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 ML20063Q0951990-08-15015 August 1990 Forwards Monthly Operating Rept for Jul 1990 for Catawba 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 ML20059K0291990-08-0101 August 1990 Forwards Comments on Reactor Operator & Senior Reactor Operator Written Exams Administered on 900730 ML20058L4061990-08-0101 August 1990 Forwards Rev 0 to Inservice Insp Rept Unit 1 McGuire 1990 Refueling Outage 6 ML20058L1811990-08-0101 August 1990 Forwards Safety Evaluation of Large Break LOCA Event Reanalysis Per 10CFR50.46 Re Peak Clad Temp Increases 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 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 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 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 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 ML20055H4131990-07-16016 July 1990 Forwards Public Version of Epips,Including RP/0/A/5000/07 & HP/0/B/1009/04 1990-09-05
[Table view] |
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bS DUKE POWER COMPANY '
PowEn BUII.DINO h 422 Socin Cncacu ST[tEl ' JB1.OTTE, N. C. 28242
. . iT:
W ILLI AM O. PA R M ER J R.
%CF P#tStCENT , TtitPMONE; Anta 704 STt*M P#0DvCYtose j 373-4063
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August 15, 1980 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Cocmission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Re: RII:VLB 50-413/80-09, 50-369/80-08, 50-491/80-02 50-414/80-09, 50-370/80-05, 50-492/80-06 50-493/80-06
Dear Mr. O'Reilly:
Please find attached a response to the infractions which were identified in the above referenced inspection report. Duke Power Company does not consider any information contained in this inspection report to be proprietary. j l
Very truly yours, .
- p y (
William O. Parker, Jr. h7 RWO:vr Attachment cc: NRC Catawba Resident Inspector I
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9 8010800 3 6-~_ . - - _ _ _ _ _ __ _ _ _ _ . - _ _ . _ _ . _ . . - . . ___ _
DUKE POWER COMPANY McGuire Nuclear Station I and 2 Catawba Nuclear Station 1 and 2 Cherokee Nuclear Station 1, 2 and 3 Response to Infraction 369/80-08-01, 370/80-05-01, 413, 414/80-09-01, 491/80-07-01, 492, 493/80-06-01.
" Temporary Record Storage Facilities - Fire Protection" Infraction:
As required by 10 CFR 50, Appendix B, Criterion XVII, and as implemented by Duke Power Company Topical Report Section 17.1.17.4 which states: " Record storage facilities are constructed, located, and secured in accordance with ANSI N45.2.9."
Contrary to the above, temporary record storage facilities in the Engineering and Services Division and Design Engineering Department fail to meet the fire protection requirements of ANSI N45.2.9-1974, Paragraph 5.6.
Response
Permanent records storage facilities for Design Engineering are constructed, located and secured in accordance with ANSI N45.2.9 temporary record storage facilities in Design Engineering are not meant to meet the fire protection requirement of ANSI N45.2.9-1974, Paragraph 5.6. Until that time when the design quality assurance records are collected, indexed and stored in the permanent records storage facility, we will continue to duplicate records as a satisfactory alternative to the establishing of a temporary record storage facility which would meet the r?quirements of ANSI N45.2.9. Design calculations will be maintained in work areas until related calculations are completed.
Then the calculations will be transferred to General Services for storage in the permanent storage facility. All design quality assurance records for a given unit will be in the permanent storage facility not later than six months following receipt of the operating license for that unit.
Records temporarily stored by Quality Assurance, Engineering and Services are supplier records and in the event of their destruction, could be duplicated ty the suppliers. In addition, the QA Department will continue to send these records to permar.ent storage facilities at the plant site will in advance of plant operation.
Response to Infraction 369/80-08-02, 370/80-05-02, 413, 414/80-09-02, 491/80-07-02, )
492,* 493/80-06-02. l
" Procedures Implementing ANSI N45.2.9 for the Corporate Records Vault" Infraction:
1 As required by 10 CFR 50, Appendix B, Criterion V, and as implemented by Duke Power Company Topical Report Section 17.1.5 which states in part: " Activities i affecting quality shall be p.escribed by ... procedures ... and shall be
, I accomplished in accordance with instructions, procedures ..." In Table 17.0-1 of Duke Power Company Topical Report, Duke Power Company has committed to implementing Regulatory Guide 1.88, Revision 2, which endorses ANSI N45.2.9. ANSI N45.2.9, Paragraph 2.1 requires that the quality assurance records system shall be defined, implemented and enforced in accordance with written procedures, instructions and other documentation.
Contrary to the above, no departmental procedures have been developed for the control and retention of records as required by ANSI N45.2.9-1974.
Response
Contrary to the stated infraction, Duke Power does have in-place departmental procedures for the control and retention of records. In fact, the existence of the procedure is referenced on pages 20, 21, and 22 of the audit report.
In point of fact, the existing facilities (i.e., the Corporate Records Vault) meet all of the requirements of ANSI N45.2.9. However, the existing acknowledged procedures fail to require or take credit for this fact. This procedure will be revised by November 1, 1980, to procedurally implement all requirements of N45.2.9 including receipt of records, preservation, and facility requirements. This action will preclude any further indications of noncompliance.
Response to Infraction 369/80-08-03, 370/80-05-03, 413, 414/80-09-03, .
491/80-07-03, 492, 493/80-06-03
" Corporate System of Audits of All Aspects of the QA Program" Infraction:
i As required by 10 CFR 50, Appendix B, Criterion XVIII, and as implemented by Duke Power Company Topical Report Section 17.1.18 which states in part "A comprehensive system of planned and periodic audits shall be carried out to verify compliance with all aspects of the quality assurance program and to determine the effectiveness of the program." Duke Power Company Topical Report Table 17.0-1, states that the program conforms to ANSI N45.2.12, Draf t 3, Revision 4, dated February 1974. ANSI N45.2.12, Draft 3, Revision 4 dated February 1974, Paragraph 3.4.2 requires that " Applicable elements of the quality assurance program shall be audited at least annually".
Contrary to the above, the following examples of failure to meet the audit requirements were identified:
- 1. A comprehensive system of audits has not been developed to assure coverage for all aspects of the QA program on an annual basis.
- 2. Audits of the minimum requirements specified by ANSI N45.2.9 Paragraph 5.7 have not been performed.
Response
A review of the existing schedule was made to assure all aspects of the Duke QA Program had either been audited or scheduled to be audited on an annual basis. Although we feel the present program is adequate, we have made revisions to now require the Audit Division to further document the system in an effort
- 1
to eliminate further misunderstanding. These procedures were issued 7/17/80.
Response to Infraction 491/80-07-06, 492, 493/80-06-06 "Use of Curing Compound on Construction Joints" Infraction:
As required by 10 CFR 50, Criterion V, Appendix B, and as implemented by Duke Power Company Topical Report Section17.1.5 which states in part:
" Activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, ... and shall be accomplished in accordance with these instructions, procedures, ..." Cherokee specification P815-1109.00-00-0001 requires concrete to be cured in accordance with the requirements of Chapter 12 of ACI 301-72. Paragraph 12.2.1.7 of ACI 301-72 specifies that curing compound shall not be used on any surface which additional con-crete is to be bonded, unless it is proven that the curing compound will not prevent bond, or unless the curing compound is removed.
Contrary to the above, curing compound was used on construction joints at Cherokee project without performance of adequate testing to demonstrate that during compound would not affect bond. The curing compound was not removed.
Response :
The design methods used to transfer shear at construction joints do not take i credit for bond as a measure of shear or tensile resistance. Where shear transfer is required in the Auxiliary and Reactor Buildng structures, the shear friction method has been employed in accordance with Section 11.15 of ACI 318-71, " Building Code Requirements for Reinforced Concrete." This method requires only a specified roughness and area of reinforcing steel to be provided at the joint for fresh concrete placed against hardened concrete.
These requirements have been specified on Duke construction drawings as appropriate for design conditions. In other safety related yard structures both shear friction and shear key methods have been employed, neither of which depend on bond for 'ser tensile or shear resistance. The requirements for shear transfer hav. 'larly been specified on the Duke construction drawings for these structures as appropriate for design conditions.
Duke Specification P81S-1109.00-00-0001, " Specification for Concrete for Category I Structures," adopted the provisions of Chapter 12 of ACI 301-72,
" Specifications for Structural Concrete for Buildings," for Cie curing of concrete. In doing so the specification failed to clarify our position on the requirements of paragraph 12.2.1.7 concerning the use of curing compounds on surfaces to which concrete or other materials are to be bonded. Section 5.4 of Duke's specification requires that joints not be bonded in accordance with Section 8.5 of ACI 301-72 except as specified on the drawings. Our intent is to specify on the drawings the joints which require bond and the method which sheuld be used to achieve bond. Since bond has not been a design factor for shear transfer in joints to date, the reference to bond requirements in ACI 301 paragraph 12.2.1.7 is not applicable.
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- We are presently engaged in rekiewing the design calculations fer all safety related concrete structures to' ensure that design requirements for shear transfer have been met at all construction joints. We have also discontinued the use of curing compounds on joint surfaces to accommodate a revised method of providing joint roughness. Construction joints are currently cured by absorptive fabrics kept continuously wet. To avoid further question of whether a noncompliance does or does not exist, Specification P81S-1109.00-00-0001 is being revised to clarify and address provisions which will be required when bond is required in consturction joints. This specification revision will be issued and ou* review of design calculations will be completed by October 1, 1980.
Response to Infraction 369/80-08-06, 370/80-05-06, 413,~414/80-09-06, 491/80-07-07, 492, 493/80-06-07
" Errors /0mmissions in Civil Design Calculations" Infraction:
As required by 10 CFR 50, Appendix B, Criterion V, and as implemented by Duke Power Company Topical Report, Section 17.1.5 which states in part: " Activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, ... and shall be accomplished in accordance with these instructions, procedures ..." Paragraph 1.1.9 of Design Engineering Procedure PR-101 requires complete presentation of the calculation such that anyone appropriate qualified could review the calculation. Paragraph 2.2.1 of Procedures PR-101 requires the checker to review data and design method used and to check the calculation step by step. Paragraph 2.3 of Procedure PR-101 requires the approver to sign and date the calculation certification page.
Contrary to the above, the following examples of failure to follow procedure were identified:
- 1. In civil design calculation number CKC 1112.12-02, (design of Cherokee NSW electrical equipment building) the concrete and reinforcing steel strength used in design were not documented in the calculation. The calculation can not be reviewed without this information.
- 2. In civil design calculation number MCC-1112.06-00-0004 (design of McGuire reactor refueling water storage tank missile wall), design shear values for walls 8 and 7 and 9 were transposed. This error was not detected by the checker.
- 3. In civil design calculation number P81C-1144.03-17 (design of Cherokee ;
primary shield wall) an incorrect value was used for the coefficient of !
friction in computation of shear friction reinforcement. This error was not detected by the checker.
- 4. The certification page for Revision 2 to calculation number P81C-1144.03-17 was not signed by the approver.
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_ Response:
Calculations CKC 1112.12-02, MCC 1112.06-00-0004 and P81C-1144.03-17 have been revised to correct deficiencies listed. Individuals performing the checking and approving of calculations will receive additional training in PR-101, Engineering Calculations. The additional training will be completed by October 1, 1980.
Response to Infraction 369/80-08-07, 370/80-05-07, 413, 414/80-09-07, 491/80-07-08, 492, 493/80-06-08 "Nonconformance Procedures" Infraction:
As required by 10 CFR 50, Appendix B, Criterion III, and as implemented by the Duke Power Company Topical Report Section 17.1.3 which requires control of the design process. Duke Power Company Topical Report Table 17.0-1, states that the program conforms, with clarification relative to immediate super-visor performing verification, to Regulatory Guide 1.64 Rev. (2) which endorses ANSI N45.2.11-1974. Section 4.3, 4.4 and 4.5 of ANSI N45.2.11-1974, as amended by Regulatory Guide 1.64, Rev. 2, 1976, Paragraph C.4, requires that procedures be established to document nonconformances with procedures for the preparation and control of drawings, specifications, and other design documents during the design process.
Contrary to the above, the Engineering Design Department QA program does not contain procedures addressing Engineering Design activities which will assure that identified noncompliances with procedures for the preparation and control of dracings, specifications and other design documents will be docu-mented, evaluated and appropriate corrective action taken.
Response
Currently, there are procedural changes under review in the Design Engineering Department formances. and the QA Department which are intended to cover design noncon-Review and ultimate reissuance of revised procedures will be implemented on or before November 1, 1980. l I
I Response to Infraction 413, 414/80-09-08
" Cable Termination Sheets" i
Infraction: i As required by 10 CFR 50, Appendix B, Criterion V, and as implemented by Topical Report, Duke 1-A, Section 17.1.5 which states in part: " Activities affecting -
I quality shall be prescribed by documented instructions, procedures, ... and shall be accomplished in accordance with these instructions, procedures ...". i Duke Power Company Design Engineering Department QA Procedure EPR-130, RI, *,,4 entitled " Electrical Division Special Drawings" requires preparation of cable ,
termination sheets to show cable terminations by color code for each cable and 24 4 provides a cable termination sheet example in Enclosure 7. !
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( 4 Contrary to the above:
- 1. Cable termination sheets for cables 1*EPC 511, 512 and 513 did not show
- cable teminations to 4160V panel 1 ETA or to diesel generator No. lA.
The cable teminations were shows as " SPARE".
- 2. Cable temination sheets for cables 1*EPC 511, 512 and 513 were not per the enclosure 7 form authori::ed by the procedure.
Response
l The cable temination sheets for the power cables identified in the inspection report will be deleted. In order to prevent a recurrence of this situation,
{ QA Procedure EPR-130 is Eting revised to clarify and accurately describe the proper u1e and purpose of cable teminations sheets. All corrective actions will ae completed by September 30, 1980.
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