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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 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 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 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 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 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 ML20216E8791999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for July 1999 for McGuire Nuclear Station 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 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 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 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 ML20210V0171999-08-13013 August 1999 Confirms Conversation Between M Cash & M Franovich on 990806 Re Mgt Meeting,Scheduled for 990917 to Present self- Assessment of Plant Performance.Meeting Will Be Held in Atlanta,Ga 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 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 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 ML20210Q3701999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr as Listed,Thirty Days Before Exam Date in Order to Register Individuals to Take Exam ML20210H7691999-07-21021 July 1999 Submits Summary of 990715 Meeting at Facility Re Presentation of Results of Most Recent Periodic Ppr.List of Meeting Attendees 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 ML20210E1931999-07-13013 July 1999 Forwards Insp Repts 50-369/99-04 & 50-370/99-04 on 990509-0619.Four Violations of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy NUREG-1431, Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation1999-07-0909 July 1999 Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation 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 ML20196J9001999-07-0606 July 1999 Informs That 990520 Submittal of Rept DPC-NE-3004-PA,Rev 1, Mass & Energy Release & Containment Response Methodology, Marked Proprietary Will Be Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20196J4381999-06-29029 June 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1,NRC Revised Info in Rvid & Releasing Rvid Version 2 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 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 ML20195D5691999-06-0303 June 1999 Submits Ltr to Facilitate Closing of Inspector Follow Up Item 50-369,370/97-15-05,re Revising Site Drawings in UFSAR Into Summary one-line Flow Diagrams,Per NRC 990327 Telcon ML20195F1851999-06-0202 June 1999 Forwards Insp Repts 50-369/99-03 & 50-370/99-03 on 990328- 0508.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20195E8771999-06-0202 June 1999 Confirms Telcon with M Cash on 990524 Re Public Meeting for 990715.Purpose of Meeting to Discuss Results of NRC Most Recent PPR ML20207D0521999-05-21021 May 1999 Informs That in Telcon on 990519 Between a Orton & Rf Aiello Arrangements Made for Administration of Initial Written Exam for McGuire Nuclear Station on 990603.Exam Will Be Administered at Catawba Simultaneously with Written Exam ML20196L1791999-05-20020 May 1999 Communicates Util Licensing Position Re Inoperable Snubbers. Licensee Has Determined That Structure of ITS Has Resulted in Certain Confusion Re Treatment of Inoperable Snubbers ML20196L1851999-05-20020 May 1999 Forwards Proprietary & non-proprietary Version of Rev 1 to TR DPC-NE-3004, Mass & Energy Release & Containment Response Methodology, Consisting of Finer Nodalization of Ice Condenser Region.Proprietary Info Withheld ML20206T4481999-05-13013 May 1999 Forwards Rev 3 to Topical Rept DPC-NE-3002-A, UFSAR Chapter 15 Sys Transient Analysis Methodology, IAW Guidance Contained in NUREG-0390 ML20206R0791999-05-13013 May 1999 Forwards Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 & Revised Monthly Operating Repts for Mar 1999 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 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 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 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 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 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 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 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 ML20210T4511999-08-10010 August 1999 Forwards Response to NRC RAI Re 981014 Standby Nuclear Svc Water Pond Dam Audit Conducted by FERC 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 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 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 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 ML20195D5691999-06-0303 June 1999 Submits Ltr to Facilitate Closing of Inspector Follow Up Item 50-369,370/97-15-05,re Revising Site Drawings in UFSAR Into Summary one-line Flow Diagrams,Per NRC 990327 Telcon ML20196L1791999-05-20020 May 1999 Communicates Util Licensing Position Re Inoperable Snubbers. Licensee Has Determined That Structure of ITS Has Resulted in Certain Confusion Re Treatment of Inoperable Snubbers ML20196L1851999-05-20020 May 1999 Forwards Proprietary & non-proprietary Version of Rev 1 to TR DPC-NE-3004, Mass & Energy Release & Containment Response Methodology, Consisting of Finer Nodalization of Ice Condenser Region.Proprietary Info Withheld ML20206R0791999-05-13013 May 1999 Forwards Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 & Revised Monthly Operating Repts for Mar 1999 ML20206T4481999-05-13013 May 1999 Forwards Rev 3 to Topical Rept DPC-NE-3002-A, UFSAR Chapter 15 Sys Transient Analysis Methodology, IAW Guidance Contained in NUREG-0390 ML20206S9151999-05-11011 May 1999 Forwards Rev 29 to McGuire Nuclear Station Selected Licensee Commitments. Section 16.11-16.2 Has Been Revised to Apply Guidance of NUREG-0133 for Performing Gaseous Effluent Dose Pathway Calculations ML20206K1341999-05-0303 May 1999 Forwards 1999 Interim UFSAR for McGuire Nuclear Station. UFSAR Update Includes Items Relocated During Improved Tech Specs Implementation.Next Regular UFSAR Update as Required 10CFR50.71(e) Is Due in Oct 1999 ML20206F3321999-04-28028 April 1999 Forwards Annual Radioactive Effluent Release Rept for 1998 for McGuire Nuclear Station. Listed Attachments Are Contents of Rept.Revised ODCM Was Submitted to NRC on 990203 ML20206E4101999-04-26026 April 1999 Forwards Four Copies of Rev 9 Todpc Nuclear Security & Contingency Plan,Per 10CFR50.54(p)(2).Changes Do Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 ML20206B4791999-04-20020 April 1999 Requests Exemption from GDC 57 Re Reactor Containment - Closed Sys Isolation Valves,As Described in 10CFR,App a for Containment Penetrations M393 & M261.Detailed Technical Evaluation & Justification for Exemption Request,Encl ML20205S9731999-04-19019 April 1999 Submits Info Re Quantity of SG Tubes Inspected,Tube Indications of Imperfections & Tubes Removed from Svc by Plugging,Per TS 5.6.8,part B 05000369/LER-1999-001, Forwards LER 99-01(S)-00 Re Contract Employee Submittal of False Info Resulting in Gaining Unescorted Access.No Licensee Planned Corrective Actions or Other Regulatory Commitments Were Identified as Result of Incidence1999-04-16016 April 1999 Forwards LER 99-01(S)-00 Re Contract Employee Submittal of False Info Resulting in Gaining Unescorted Access.No Licensee Planned Corrective Actions or Other Regulatory Commitments Were Identified as Result of Incidence ML20205P8891999-04-13013 April 1999 Forwards Monthly Operating Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for Feb 1999 Encl ML20206K3561999-04-13013 April 1999 Forwards Revised McGuire Nuclear Station Selected Licensee Commitments (SLC) Manual. Significant Changes Are Marked by Vertical Bars on Right Margin ML20205K5131999-04-0707 April 1999 Forwards Complete Response to NRC 981209 & 990105 RAIs on Question 11 Re LARs for McGuire & Catawba Nuclear Stations. Addl Info Received from W & Contained in Encl W ML20205B6011999-03-23023 March 1999 Requests That NRC Place Technical Interface Agreement 97-02 Re URI 96-11-03,raising Operability & Design Criteria Conformance Issues Re Hydraulic Snubbers Installed at Plant & NRR Response on Dockets to Provide Record of Issue ML20205C4611999-03-23023 March 1999 Submits Correction to Violation Against 10CFR50 App B, Criterion VII, Control of Purchased Matl,Equipment & Svcs, Issued to McGuire Nuclear Station on 980807 ML20205B6161999-03-23023 March 1999 Provides Addl Info & Correction to Typo in Re License Bases Record Change Re License Amend Submittals ,approved as FOL NPF-9 & NPF-17,amends 184 & 166, respectively.Marked-up TS Pages,Encl ML20204J0051999-03-19019 March 1999 Forwards Response to 990127 & 28 RAIs Re GL 96-05 for Catawba & McGuire Nuclear Stations ML20204E1791999-03-18018 March 1999 Reflects 990318 Telcon Re License Bases Record Change for License Amend Submittals ,approved as Amends 184 & 166,respectively for Licenses NPF-9 & NPF-17.TS Pages Encl ML20204C8821999-03-15015 March 1999 Forwards Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for Jan 1999 Encl ML20207C2071999-02-25025 February 1999 Informs of Revised Expected Submittal Date of Proposed License Amend Presented at 990127 Meeting Re Soluble Boron & Boraflex.Util Plans to Submit Proposed License Amend in First Quarter of 1999 ML20207C7691999-02-22022 February 1999 Forwards Annual Occupational Radiation Exposure Rept for 1998. Rept Provides Tabulation of Number of Station,Utility & Other Personnel Receiving Exposure Greater than 100mRem/yr Followed by Total Dose for Each Respective Worker ML20207C6851999-02-22022 February 1999 Forwards Revised TS Bases Pages,Reflecting Removal of SI Signal on Low Steamline Pressure on Page B 3.3.2-16 & Adding Clarification for Increasing Hydrogen Recombiner Power During Testing on Page B 3.6.7-4 ML20206S3341999-01-28028 January 1999 Forwards Proprietary & non-proprietary Responses to NRC 981209 & 990105 RAIs Re Util Lars,Permitting Use of W Fuel at McGuire & Catawba Stations.Proprietary Info Withheld,Per 10CFR2.790 ML20199E0081999-01-12012 January 1999 Forwards MOR for Dec 1998 & Revised MOR for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 ML20199C9861999-01-0707 January 1999 Forwards Annual Lake Norman Environ Summary Rept for 1997,as Required by NPDES Permit NC0024392,including Detailed Results & Data Comparable to That of Previous Years.With Corrected Pages 3 & 19 to 1994-95 Lake Norman Creel Rept 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) 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 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 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 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 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 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 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 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 ML20059K0291990-08-0101 August 1990 Forwards Comments on Reactor Operator & Senior Reactor Operator Written Exams Administered on 900730 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 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 ML20055F7721990-07-13013 July 1990 Forwards Monthly Operating Repts June 1990 for McGuire Nuclear Station Units 1 & 2 & Status Rept for May 1990 ML20044B0561990-07-0303 July 1990 Forwards Public Version of Epips,Consisting of RP/0/A/5700/02 & RP/0/A/5700/03 & RP/0/A/5700/04.W/ Dh Grimsley 900716 Release Memo ML20044A7941990-06-19019 June 1990 Forwards Public Version of Epips,Including HP/0/B/1009/06, HP/0/B/1009/10 & HP/0/B/1009/20 ML20043H5541990-06-18018 June 1990 Forwards Supplemental Info to Tech Spec Rev Request Re Auxiliary Bldg Filtered Ventilation Sys ML20043G1531990-06-15015 June 1990 Forwards Monthly Operating Repts for May 1990 & Corrected Unit Shutdowns & Power Reductions for Apr 1990 ML20043G1741990-06-0707 June 1990 Responds to Request for Addl Info Re BAW-10174, Mark-BW Reload LOCA Analysis for Catawba & Mcguire. Correct RCS Operating Pressure Would Be 2,250 Psia as Identified in Table 3-1 ML20043G3451990-06-0707 June 1990 Forwards Proprietary Response to Request for Addl Info Re Topical Rept BAW-10174, Mark-BW Reload Safety Analysis for Catawba & Mcguire. Response Withheld ML20043G7171990-06-0606 June 1990 Forwards Population Dose Analysis Summary for Plant Liquid Release Pathways Based on 1986 Release Estimates ML20043G6321990-06-0505 June 1990 Responds to Violations Noted in Insp Repts 50-369/90-01 & 50-370/90-01.Corrective Actions:Memo Issued Reemphasizing Importance of Frisking & Outlining Frisking Requirement & Personnel Counseled Re Completing Required Documentation ML20043G6281990-06-0404 June 1990 Advises That Corrective Actions Re Departmental Interface Issues to Resolve & Train on Revised Directive Will Be Completed by 900901,per Insp Repts 50-369/89-01 & 50-370/89-01 ML20043F4761990-05-30030 May 1990 Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Consisting of Rev 20 to CMIP-13 & Deletion of CMIP-15 & CMIP-17.W/900612 Release Memo ML20043B5691990-05-23023 May 1990 Advises That Responses to Violations Noted in Insp Repts 50-369/90-01 & 50-370/90-01 Will Be Delayed Until 900601 ML20043C0781990-05-22022 May 1990 Responds to Violations Noted in Insp Repts 50-369/90-04 & 50-370/90-04.Corrective Actions:Correct Procedure Adherence Reemphasized to Job Supervisor & Engineering Group Involved in Authorization for Torque Change ML20043B9351990-05-16016 May 1990 Forwards Public Version of Epips,Including HP/1/B/1009/15 & HP/2/B/1009/15.W/DH Grimsley 900529 Release Memo ML20043A1041990-05-15015 May 1990 Forwards Monthly Operating Rept for Apr 1990 & Corrected Mar 1990 for McGuire Nuclear Station Units 1 & 2 ML20042G8221990-05-10010 May 1990 Forwards Addl Info Re Events Leading to 900509 Emergency Tech Spec (TS) Request Re TS 4.6.1.8,per Ds Hood 900510 Telcon & Requests That Changes Also Be Made to Unit 2 Ts. Proposed TS Encl ML20043A8621990-05-10010 May 1990 Forwards Info for Facility 1990 Refueling Outage Re Steam Generator F* Tubes & Tubes Removed from Svc or Repaired ML16152A9621990-05-0909 May 1990 Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 35 to CMIP-1,Rev 26 to CMIP-2,Rev 31 to CMIP-4,Rev 35 to CMIP-5,Rev 40 to CMIP-6,Rev 39 to CMIP-7 & Rev 26 to CMIP-8.W/DH Grimsley 900517 Release Memo ML20042G8331990-05-0808 May 1990 Forwards Info for Facility Tube Rupture Outage Re Steam Generator Inservice Insp,Per Tech Spec 4.4.5.5 & 6.9.2 ML16152A9531990-05-0202 May 1990 Forwards Proprietary DPC-NE-2000P-A & Nonproprietary DPC-NE-2000-A, DCHF-1 Correlation for Predicting Heat Flux in Mixing Vane Grid Fuel Assemblies. Proprietary Rept Withheld ML20042F2611990-04-30030 April 1990 Forwards Technical Evaluation That Concludes Fireproofing of Supports for safety-related HVAC Ducts Not Required & Amends Fire Protection Commitment Re HVAC Sys Support Fireproofing ML20042F8331990-04-26026 April 1990 Forwards Public Version of Revised Epips,Including Change 0 to RP/0/A/5700/01,RP/0/A/5700/02 & RP/0/A/5700/03 ML20042E0631990-04-13013 April 1990 Forwards Monthly Operating Repts for McGuire Nuclear Station for Mar 1990 & Feb 1990 Rept Re Personnel Exposure 1990-09-04
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DUKE POWEH COM PANY Powicu liciwiso 422 Sot:Tu Cir c ucri STunce:T, CII ARI.OTTE, N. C. 2n242 www o. ma n n. s n. February 1, 1979
/t C F P#ts:OrNY 'r . C Pw C N E ' A D E 4 7C4 SffaM PRODUCT'ON 3 73 4CS 3 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. Robert L. Baer Light Water Reactors Project Branch No. 2
Subject:
McGuire Nuclear Station Docket Nos. 50-369 and 50-370 Preservice Inspection Plan
Dear Mr. Denton:
Your letter of April 26, 1978 transmitted questions 121.15 and 121.16 requesting additional information with regard to the McGuire Unit No. 1 preservice inspection plan. Our response to this request was trans-mitted by a May 31, 1978 letter to .:r. Edson G. Case. After further dir.eussions with members of the NRC staf f Duke provided more detailed request for relief from ASME Section XI requirements. These requests for relief are summarized in Attachoent 1.
Attachment 2 consists of requests for relief MC-1-025 through MC-1-031.
MC-1-025 and MC 326 cc splete the known requests for relief from ASME Claso II, requirements. Requests for relief MC-1-027 through MC-1-031 are further requests for relief frem ASME Class I and Class II require-ments which supplement our May 31, 1978 letter.
It is requested that requests for relief MC-1-014 and MC-1-015, trans-mitted by our July 24, 1978 letter, be withdrawn. It has been deter-mined that there are no welded supports on Class I systems thus making MC-1-014 and MC-015 unnecessary.
Very truly yours,
-
pa.~ a. a; l[.
g/ William O. Parker, Jr. ~
GJP:ses Enclosure O s
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McGuire Nuclear Station
,
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. ATTACHMENT 1 Relief Request Summary Date Of Relief Submittal Serial No. Code Class Description of Component / Relief July 24, 1978 MC-1-001 N/A Request for relief from requirement of ASME Boiler & Pressure Code Section /,
1971 Edition thru Winter 1972 Addenda.
Article 6, Paragraph T-630.
"
MC-1-002 I Reactor vessel primary nozzle to safe-end welds.
"
MC-1-003 I Pressurizer Longitudinal and Circum-ferential weld seams-National Board Number 68-123.
"
MC-1-004 I Pressurizer integrally welded supports-National Board Number 68-123.
"
MC-1-005 I Steam Generator Circumferential weld seams-National Board Nos. lA: 68-107, IB: 68-108, IC: 68-109, ID: 68-110
"
MC-1-006 I Steam Generator Nozzle to safe-end welds-National Board Nos. same as MC-1-005.
"
MC-1-007 I Pressurizer safe-end to surge line-National Board No. 68-213.
"
MC-1-008 I Piping-Longitudinal and Circumferential weld seams.
"
MC-1-009 I Branch piping welds exceeding 4 inches (NPS) - Visual Inspection impractical.
"
MC-1-010 I Branch piping welds exceeding 4 inches (NPS) - 4 inch NPS changed to 6 inch NPS.
"
MC-1-011 I Branch Piping Welds 4 inch (NPS) &
smaller - Visual Inspection impractical.
"
MC-1-012 I Branch Piping Weids 4 inch (NPS) &
smal:er - 4 inche NPS to 6 inch NPS
"
MC-1-013 I Piping Socket Welds
"
MC-1-014 I Piping Integrally Welded Supports
"
MC-1-015 I Valve Integrally welded Supports
"
MC-2-001 N/A Same as MC-1-001 September 5,1978 AC-1-016 I, II All componente requiring preservice hydrostatic test.
"
MC-1-017 I ASMS Class I valves > 3 inches (NPS)
September 25, 1978 MC-1-018 I Reactor Coolant Pumps lA, IB, IC, ID
"
MC-1-019 I Reactor Coolant Pumps lA, IB, 1C, ID Lower Seal Housing Belts (12 per pump)
.
McGuire Nuclear Station
.
,.
ATTACIIMENT 1
'
Page 1%o Relief Request Summary Date Of Submitta? Serial No. Code Class Description of Component / Relief September 25, 197's MC-1-020 I Reactor Coolant Pumps lA, 1B, IC, ID Lower Seal llousing Ligament Area
"
MC-1-021 I Reactor Vetsel licad, Control Rod Drive Penetratfor.s - National Board No. 20766
"
MC-1-022 I Reactor Vessel Incore Instrument Penetrations - National Board No. 20766
"
MC-1-023 I Control Rod Drive Mechanisms llousing Welds
"
MC-1-024 I Reactor Vessel Closure IIead-National Board No. 20766
.
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Mr. Ilarold R. Denton, Director February 1, 19'9 DUKE POWER COMPANY Requests For Relief From Insecvice Inspection Requirement McGuire Nuclear Station ATTACIIMENT 2
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Serial t;o. _MC-1-025
_.
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, Page 1 of 2
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DUKE POWER COMPANY Request For Relief From inservice inspection Requirement Station: McGuire Unit: 1 Reference Code: ASME Boiler and Pressure Vessel Code, Section XI, 1971 Edition through Winter 1972 Addenda
- 1. Conponent for which exemption is requested:
- a. Name and identification Mumber:
Residual Heat Removal (ND) Heat Exchangers (2)
National Board Numbers 635, 636
- b. Function:
Primary Coolant Heat Removal
- c. ASME Section ll1 Code Class:
Class 11
- d. Valve Category: NA
- 11. Reference Code Requircuant that has been determined to be ir.pra c t i ca l :
Category C-B ltem C1.2 Volumetric examination of nozzle to vessel welds (2 per heat exchanger) . Due to welded collar, the nozzle to vessel welds are inaccessible. See attachment 1.
111. Basis for Requesting Relief Material - Shell SA-240 Type 304 SS, Nozzles SA312 Type 304SS Estimate of preservice examination performed - 0%
Original fabrication examination - Radiography and dye penetrant examina* ion Measures which would be required to make the area accessible - Removal o ?
the welded collars Reference Drawing - Sketch Attached
a Serial No. MC-1-025
,
Page 2 of 2 DUKE POWER COMPANY Reque s t Fo r Re l i e f F rcr1 Inservice inspection Requirement 111. Basis for Requestin9 Relief (cont.)
To grind off the welded collars would not justify the high cost and loss of time to inspect the nozzle to vessel welds. The shop examinations provide adequate assurance of component reliability.
IV. Alternate Examination:
The fillet welds attaching the collar to the nozzle and shcIl will be examined with dye penetrant. The vessel has been hydrostatically tes ted wi th no evidence of leakage.
V. Impicmentatico Schedule:
Inservice inspections will include a surface examination of the collar velds and hydros tatic tes ts.
1 A ttae u e b 1 Io
,
.
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-
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- Serial IJo. MC-1-026
- - . Page 1 of 2
,
DUKE POWER C0tiPANY
'
Request For Relief Fran Inservice Inspection Requirement Station: McGui re Unit: 1 Reference Code: ASME Boiler & Pressure Vessel Code, Se .on XI, 1971 Edition through Winter 1972 Addenda
- 1. Component for which exemption is requested:
- a. flame and Identification Number:
Steam Generators I A, IB, I C, ID National Board Numbers 68-107, 68-108, 68-109, 68-110 respectively
- b. Function:
Primary to Secondary coolant heat exchanger
- c. ASME Section lli Code Class:
Class 11
- d. Valve Category: NA
- 11. Reference Code Requirement that has been determined to be impractical:
Category C-A Item Cl.1 of Table ISC-261 volumetric examination of steam generator transition cone to lower shell barrel circumferential weld. Due to location of seismic res.raint, approximately 60% of the weld is obscured.
Ill. Basis for Requesting Relief Material - ASME-SA-533, Grade A Class 2 Estimate of preservice examination performed - 40%
Original fabrication examination - Radiography Measures which would be required to make the area accessible - Removal of seismic restraint.
Reference Drawing - Sketch Attached
Serial No. MC-1-026
Page 2 of 2
.
.
DUKE POWER COMPANY Request Fo r Re l i e f f rom inservice inspection Requirement 111. Basis for Requesting Relief (cont.)
The welds in question have been ultrasonically tested from one side using 0 , 45 , and 600 transducers. Due to the location of the restraint, it is impossible to perform the 0 s can on the weld centerline or the 45 and 60 scans f rom the lower side of the weld.
All other steam generator welds are accessible. It is believed that the limited scan plus the periodic hydrostatic tests provide adequate assurance of weld integrity. The high cost in time and money does not Justify relocating the seismic restraint.
IV. Alternate Examination:
None V. Implementation Schedule:
Inservice inspections will be performed by using the limited scan described above.
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Page 1 of 2
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DUKE PCWER COMPANY Request For P.clief From Inservice inspection Requirement Station: McGui re Unit: , i Reference Code: ASMS Boiler and Pressure Vessel Code, Section XI, 1971 Edition through 1972 Winter Addenda I. Component for which exemption is requested:
- a. Name and Identification Number:
Steam Generators I A, IB, IC, ID National Board Numbers, 68-107, 68-108, 68-109, 68-110 respectively
- b. Function:
Primary to Secondary coolant heat exchanger
- c. ASME Section III Code Class:
Class I
- d. Valve Category:
NA II. Reference Code Rcquirement that has been determined to be impractical:
Category F l tem 3.3 of Table IS-261 Volumetric examination of primary nozzle to safe end welds. Due to presence of ground out areas and the contour of the nozzle, the safe-end weld cannot be fully inspected.
,
'
III. Basis for Requesting Relief Material - ASME SA-216 Grade WCC casting, buttered with Type 309 austenitic stainless steel, welded to centrifugally cast ASME SA-351 CF8A stainless steel piping.
Estimate of Preservice Examinaton Performed - 90% volumetric, 100% surface Original Fabrication Examination - Radiography and liquid penetrant Measures which would be required to make the area accessible - Cosmetic welding then post weld heat treatment Reference Drawing - Sketch attached
.
1 Serial fio. MC-1-027-.. _ -
Pcge 2 of 2
.
.
DtlKE PC'.!ER COMP /d;Y Request for Re1ief Fro, inservice inspec t ion Requirer:ent lil.
Basis for Requestin9 Relief (cont.)
The ground out areas are present on all eight nozzle to safe-end welds and vary in depth from 1/32 inch to 1/8 inch. As can be seen from the attached sketch, the ground-out areas only slightly limi t the ultrasonic scan. Both the manufacturer and an cutside consultant have recommended that cosmetic welding not be performed. Because of our concern that cosmetic welding might be deleterious to the weld joints, this request for relief is submitted.
IV. Alternate Examination:
The welds have been examined ultrasonically, visually, and with dye penetrant in accordance with the Section XI Code.
V. Implementation Schedule:
Inservice inspection will be performed in accordance with the Section XI Code Edition specified by 10CFR55.55 a, paragraph (g) .
In addition, the welds will be examined using liquid penetrant every third refueling outage.
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. Serial No, MC-1-028 Page 1 of 2 DUKE POWER COMPANY Request For Relief Fron Inservice inspection Requirement S ta tion: McGuire Unit: , 1 Reference Code: ' ASME Boiler and Pressure Vessel Code, Section XI, 1971 Edition through Winter 1972 Addenda
- 1. Component for which exemption is requested:
- a. Name and identification Number:
Containment Penetration Assemblies:
Type 1 - Main Steam (4) Type 111-3 -RHR discharge to hot legs (1)
Type 11 - Feedwa ter (4) Type 111 Upper Head injection (2)
Type 111 RHR discharge to cold legs (2)
Type lil RHR supply (1)
- b. Function:
Provide air tight seal for piping through the containment boundary
- c. ASitE Section lli Code Class:
Class 11
- d. Valve Category:
NA II. Reference Code Requirement that has been determined to be impractical:
Ca tegories C-F, C-G - I tem C2.1 of Table I SC-261 vol ume t ri c exami na t ion of piping circumferential butt welds. Due to the design of the penetration assemblies, the penetration flued head to process pipe welds are inaccessible.
In addition ~, the Type I and Type 11 penetration flued head to guard pipe welds are inaccessible.
'
III. Basis for Requesting Relief Reference Drawings - See figures 1, 2, 3, 4 attached Material - See figures 1, 2, 3, 4 Estimate of Preservice Examination Performed - 0% of the inaccessible welds Original Fabricaton Examination - Radiography. Type I (Main S team) fl ued head to guard pipe welds received penetrant and ultrasonic examination Type il (feeJaater) flued head to guard pipe welds were exan.ined by radiography.
Measures whien would be requi red to make the areas accessible - complete redesign, manufacture, and installation.
.
Seriai !!o . MC-1-028 I'cge 2 of 2
. .
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DUKE PO*ilER COMPANY Request for Relief Frcn Inservice inspection Require. rent 111. Basis for Requesting Relief (cont.)
At the time of purchase, the penetration assemblies were state of the art in design and manufacturing technique. Redesign and replacement would result in extended delay and enormous cost. Component integrity can be assured with examination of similar welds in the process pipe coupled with hydrostatic tests and penetration leak tests.
IV. Alternate Examination:
Piping systems have been hydros tatically tested and penetrations will be leak tested.
V. Implementation Schedule:
Inservice inspection will consist of testing described in IV above.
.
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Serial No. MC-1-029
- Page 1 of 2 DUKE POWER COMPANY Request For Relief From inservice inspection Requirement S ta tion: McGui re Unit: ,
I Reference Code: ASME Boiler and Pressure Vessel Code, Section XI, 1971 Ed', tion through Winter 1972 Addenda
- 1. Component for which exemption is requested:
- a. Name and identification Number:
Main Steam and feedwater systems See attached Figures 1, 2, 3,4,5,6,7,8
- b. Function:
Circulate secondary coolant
- c. ASME Section lli Code Class:
Class 11
- d. Valve Category: NA
- 11. Reference Code Requirement that has been determined to be impractical:
Category CG, item C2.1 of Table IEC-261, Volumet ric Examination of piping ci rcumfe rential butt welds. Due to presence of guard pipe, approximately 16% of the feedwater and 75% of the Main Steam welds are inaccessible.
'
III. Basis for Requesting Relief Reference Drawings - see figures 1 through 8 Material - Listed on reference figeres Estimate of Preservice Examination Performed - 0% on inaccessible portions 100% on accessible portions Original fabrication examinaton - 100% Radiography heasures which would be required to make the areas accessible - Removal of the guard pipe
.
Serial flo MC-1-029
. Pcge 2 of 2
.
4 DUKE POWER C0!iPANY Request for Relief From Inservice inspection Requirement Ill.
Basis for Requesting Relief (cont.)
The guard pipe was designed and installed for pipe rupture and jet impingement protection required by NRC directives. Section XI requi rements to inspect Class 11 piping systems had not been developed at the tine of system design.
Component integrity can be assured by examining the accessible welds (Section XI only requires examining 50% of the welds at s tructural discontinui ties, and this number is further reduced by applying the multiple s t ream concept) and hydros ta ti c tests. The purpose of the guard pipe and support systems is to maintain plant safety in the unlikely event of system f a i l u re. We believe the extreme neasures required to make the areas accessible without compensating increase in the level of quali ty assurance do not justify the hl h cost and. loss of time.
IV. A'IternSteExamination:
No alternate examination is possible.
V. Implementation Schedule:
Preservice examination has been completed on the accessible welds.
Inservice examinations will be p;rformed on the accessible welds as required by the Section XI speci fied by 10CFR50.55a paragraph (g) .
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T Serial No. MC-1-030
'
.. Page 1 of 2
.
DUr.E POWER COMPANY Request For Relief Froa Inservice inspection Requirement ,
.
S ta t ion: McGuire Unit: ,
I Reference Code: 'ASME Boiler & P ressure Vessel Code, Section XI, 1971 Edition through Winter 1972 Addenda
- 1. Component for which exemption is requested:
- a. Unme and identification Number-
,
Main Steam System welded restraint attachments Rl A through R8A RIC through R8C Rla through R8B RlD through R8D
- b. Function:
Wear pads welded to main steam piping encased by guard pipe
- c. ASitE Section 111 Code Class:
Class 11
- d. Valve Category:
NA II. Reference Code Requirement that has been determined to be impractical:
Ca tego ry C-C , I tem C2.4 of Table ISC-261 surface examination of integrally welded support-to pipe welds. Due to the presence of guard pipe the welded wear pads of la above are inaccessible.
Ill. Basis for Requesting Relief Material - SA-515 Grade 70 plate or SA-155 KC70 pipe wear pads fillet welded to SA-106 Gr C main steam piping Estimate of Preservice Examinaton Performed - 0%
Original Fabrication Examination - Magnetic particle surface examination Measures which would be required to make the areas accessible - remova l of the guard pipe Reference Drawing - Sketch attached.
.
F Serial i;o MC-1-030
- . .
, l'q;e 2 of 2
.
.
DUKE PO',f:R COlPMlY ,
hequest for r, e 1 i c f F rce,
,
inservice i nspec t ion Requ i re:.:en t Ill. liasis for heques t ing nelie f (cont.)
The main steam guard pipe was designed and purchased before there was a Section XI req u i remen t to inspect Class 11 components. These wear pads are only subject to compress ive stresses . The welds have been verified defect f ree by original fabrication examination.
Component integrity can be assured by inspecting similar system welds
-nd hydrostatic tests.
IV. Alternate Examination:
No alterndte examination is possible.
V. Implementation Schedule:
The system is installed and field hydrostatically tested.
I nse rvi ce inspections will not be poss:ble because of inaccessibility.
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* ' ' Page 1 of 2 e
'
DUF.E PL./ER COMPANY
.
Request for Relief Frca
' Inservice inspection Recui rcment .
S ta t ion: McGuire Unit: ,
I Reference Code: ASME Boiler & Pressure Vessel Code, Section XI, 1971 Edition through Winter 1972 Addenda
- 1. Component for which exemption is requested:
- a. llame and Identification Number:
'
Feedwate r sys tem welded attachments , CF-H1 and CF-H2.
See attached sketch,
- b. Function:
Wear pade welded to feedwater piping encased by guard pipe
- c. ASME Section 111 Code Class:
Class 11
- d. Valve Category:
NA II. Reference Code Requirement that has been determined to be impractical:
Ca tego ry C-C , item C2.4 of Table ISC-261 surface examination of integrally welded support-to pipe welds. Due to the presence of guard pipe the wear pads are partially inaccessible.
Ill. Basis for Requesting Relief Material - CF-H1 and CF-H2 each cbnsists of 4 segments of ASME SA-106 Gr. B pipe 3/8 in x 8 ir. x 6 in fillet welded to ASME SA-106 Gr. B pipe.
Estimate of Preservice Examination Area Accessible - 35%
Original Fabrication Examination Performed - Magnetic particle surface examination Measures which would be required to make the area accessible - Removal of the guard pipe Reference Drawing - Sketch attached.
.
Serial I;o. MC-1-031
__
. .. , Page 2 of 2
,
.
.
DUKE PO'..T R C0".PA"Y -
Request Fo r P,e l i e f F rca inservice i n s;,;-c t i e n Re qu i r ca:e n t Ill. i;as i s for i cques t ing Relief (cont.)
The feedwater guard pipe was designed and purchased before there was a Section XI req ui remen t to inspect Class 11 components. The welds have been veri fied defect f ree by original fabrication examination. Component integrity can be assured by inspecting the 35% of the accessible area, inspe,ction of similar system welds, and hydrostatic tests.
IV. Alternate Examination:
No alternative examination is possible.
V. Implementation Sciedule:
The system is installed and field hydrostatically tested. The accessible areas will be examined in January 1979 Inservice '
examination of the accessible areas will be in accordance with the Section XI code required by 10CFR50.55a, paragraph 9
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