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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 POWER GOMPANY P.O. Box 33180 CHARLOTTE, N.C. 28242 II AL II. TUCKER TELEPHONE ver e perssorwr (704) 373-4531 anxa. ram risope.rtums Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: McGuire Nuclear Station Docket No. 50-369
Dear Mr. Denton:
The purpose of this letter is to provide a summary of the results of the eddy current testing (ECT) performed on the Unit 1 steam generators and to outline the proposed operating plans for the unit.
Duke Power Company has evaluated operation for an additional 30 days at 75 percent power using information from previous ECT. Attachment 1 is the evaluation performed to justify this operation. Attachment 2 provides information from recent ECT examinations. Although we have evaluated operation at 75 percent power for 30 days and are requesting your concurrence for this period of time, it is our intent to operate above 50 percent power only during periods of time when additional power would normally be purchased external to the Duke Power system at a cost higher than oil generation.
This situation, if it occurred at all, would be expected to occur only under very severe weather conditic7s and would likely be short term. The 00f reason for this limitation is not due to any safety concerns, but is due j
to economic, availability and long term plant performance concerns. p'.
The NRC Staff evaluation of the proposal will of necessity have to consider b,fiLAM the full 30 days at 75 percent power, but it is important that the Staff understand Duke's intention to limit operation above 50 percent power as c . C W' s T*gD described above.
g, Q:th@Y Currently, an outage is scheduled for mid-January 1983 to install the steam bO [
generator modification. This schedule is predicated on completion of all Westinghouse analyses, manufacture and delivery of hardware and approval ygg T of the Design Review Panel report by the NRC within this time frame. Since Q there remain many uncertainties, this schedule is subject to change. Duke f/. k ogi n wM.
Power Company would continue to operate McGuire Unit 1 at 50 percent power l
(as qualified above) until the modification is ready for installation but would shut down no later than April 1, 1983 for the next ECT.
l I
l If there are any questions regarding this proposal, we would be pleased to discuss them with you.
8212170290 821215 PDR ADOCK 05000369 p PDR 1 _ -
Mr. Harold R. Denton, Director December 15, 1982 Page 2 Very truly yours, uVSxfI Hal B. Tucker i CAC/php cc: Senior Resident Inspector McGuire Nuclear Station Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303
ATTACHMENT 1 MCGUIRE NUCLEAR STATION Justification For Additional Operation at 75% Power Introduction Since the problem of premature tube wear in Westinghouse Model D steam generators was discovered in 1981, Duke Power Company has operated McGuire Unit I at restricted power levels and has performed steam generator inspections at frequent intervals. This manner of operation, which is consistent with the guidance contained in Regulatory Guide 1.83 and 1.121, was a cautious attempt to establish the extent that the McGuire 1 steam generators were affected and the wear rate as a function of power level. The most recent inspection of McGuire, performed after the second of two 30 day periods of operation at 75% power, has provided the data which permits accurate determination of the tube wear rate and the effects of additional operating time at 75% power.
Results of Previous Inspections In July,1982, the four steam generators at McGuire 1 were inspected following
- a period of operation which included 30 days at 75% power. At that time, only one steam generator tube showed significant wear (tube 49-40 in steam i
generator C) and a wear rate prediction was made based on that single tube.
The calculated wear rate at that time bounded that of all other worn tubes and could therefore be used as an estimate of the additional wear which would l occur during another 30 day period of operation at 75% power. In our report to NRC, it was noted that this single tube would wear to the plugging limit (40% through wall by Technical Specifications) and that no other tubes would show total wear as large as 40%. On the basis that the total number of i affected tubes was small, and that signficiant wear appeared on only one tube,
- we recommended and NRC accepted additional operation including another 30 day
( period at 75% power.
Results of Most Recent Inspection In November, 1982, McGuire I was again shut down for steam generator inspection. This inspection was performed and evaluated in the same manner as l the July, 1982, inspection in order to ensure that the most accurate measure l of additional steam generator tube wear could be made. The results of this inspection are reported in detail in Attachment 2. As expected, steam generator tube wear continued to progress due to operation at 75% power.
l Significant wear indications (through wall depths greater than 12% or 5 mils) l appeared on 21 tubes, including tube 49-40 in steam generator C. As predicted l following the July, 1982 inspection, this tube had worn to a through wall depth just below the 40% plugging limit. This tube has been taken out of service by plugging. Five other tubes of this group were also plugged, though the measured defect depth was much less than 40%; this is discussed further in the section below on preventive plugging. The total number of tubes 1
I
- . s _ _ _
4 s
r b .
showing any indication of wear is 67, including 41 which showed no indication of wear at the July, 1982 inspection. Thi r. amber of worn tubes represents 12% of the total tubes in rows 47, 48, and 49 and 0.3% of the total number of tubes in the four steam generators.
Calculation of Tube Wear Rate Duringeachofthepreviousoperatingperiods,moakoperationhasoccurredat 50% power and below. Based on operation at the Almaraz 1 ur.it in Spain, '
operation at 50% power (equivalent to 52% at McGuire, due to higherifeedwater flow) for 3000 hours0.0347 days <br />0.833 hours <br />0.00496 weeks <br />0.00114 months <br /> produces no measurable wear. It should be noted that Almaraz 1 operated at full power for several months prior to the discovery of the tube wear problem and contains many tubes with wear penetration higher than the largest wear seen at McGuire'1. Accordingly,"it is concluded that operation at 50% and below does not cont.ribute to the wear seen at McGuire 1.
Operation during each previous period at McGuire has included approximately 30 days 75% power. Though the total number of affected tubes remains small, sufficient data has been gathered to support the following conclusions:
- 1. When tubes are unworn, or when wear volunes are very small (on the order of 10~4 cubic inches or less), wear rat'es are very small.
~
- 2. Once tube wear progresses to the point that the. total metal removed is N10 4 cubic inches (this corresponds to approximately 12% through wall),
then the wear rate increases. An examination of the data from the July, 1982, inspection showed nine tubes with wear indications of N10~4 cubic .
inches. These nine tubes now have wear indications between 2.6 x 10 3 and 3.4 x 10~3 cubic inches. Accordingly, an upper bound for tube wear may be established as 3.4 x 10 3 cubic inches per 30 day period at 75%
power. The tube with the highest wear tube 49-40 in stearJ generator C, ^ ,
' had a wear volume of 2x 10 3 cubic inches in ' July, 1982. The measured ,
volume based on the most recent inspection is[5.2 x 103 cubic inches.
It can therefore be concluded thit a wear rate of 3.4 x 10 3 cubic inches per 30 day operating period is consistent with the data from all worn tubes and applies as long as the total wear t mains below the plugging-limit of 40% through wall' .
Wear Projection for Additional 75% Power Operation If the wear rate determined above susedtoprojecttheconsequencesofan i
I additional 30 day period of or' u .on at 75%, the following conclusions may be stated: ,
- 1. Two additional tube. ilt . guire plugging based on the plugging limit of
, 40% through wall. Tr:2se two (Lbes will have indications less than 50%.
l 2. Twenty-three tubes which currently have wear indication of *104 cubic
' inches will have indications of 73.5 x 10 3 cubic inches. This wear volume corresponds to a thrc, ugh wall depth of less than 25%.
2 4
_ , _,.m..--._-r,-~- _-__e_. -
~
preventive Plugging Once the wear rate was calculated based on the previous operating period, it was decided tha'. five tubes should be preventively plugged due to the progression o' tube wear. All of these tubes showed wear volumes of E3.4 x 10_3 cubic inche: or 23-25% through wall. It was noted that these tubes would grow beyono the plugging limit (to approximately 56% through wall) during a subsequent 30 day operatieg period at 75% power. The wear rates for these five tubes were equal to or less than the wear rate discussed above.
Long Te p Consequence of Additional Tube Wear Because the tube wear rate at 75% power is not zero, further operation at 75%
i . power will cause some additional tube wear. Ilowever, the magnitude of tube
!? wear and the total number of tubes affected remains small. From previous operation, an estimate of the wear rate at 75% has been established and this calculated wear rate is not expected to change in the next operating period.
An assessment of the short term consequences of an additional 30 days operation at 75% power shows that these consequences are acceptable.
The modification that Westinghouse has proposed is designed to be effective for units like Ringhals 3 and Almaraz 1 which have more severe initial wear than McGuire will have following the next operating period. It is concluded that the condition of the steam generator tubes in McGuire will not adversely affect the ability of the modification to eliminate the tube wear problem.
Duke Power Company has also considered whether the worn areas will cause the possibility of accelerated corrosion and premature tube failure. The chemical environment in the preheater area, being that of feedwater rather than steam generater bulk water, is more favorable from a corrosion standpoint. The i
temperature at the outer wall of the tubes is less than cold leg temperature and therefore much less than the temperature at which corrosive attack has
, adversely affected steam generator tubes. Finally, in the first few rows of i the preheater, flow velocities will remain high after the modification, pre-l cluding sludge deposition. We conclude that the worn condition of the tubes will have no significiant effect on the ability of the tubes to resist corrosion.
l Over the 40 year life of the steam generator, a number of corrosion mechanisms can be expected to be active in the tube bundle, causing a gradual deterioration
( in the condition of the tubes. The chemistry program at McGuire is expected i to reduce the rate of this deterioration to acceptable levels. The tubes in
( the front row of the preheater, while signiciantly affected by wear early in I
life, are expected to be much less affected by corrosion later. Accordingly, the wear created by this early operation is not expected to affect the 40 year lifetime of the worn tubes.
!\
Conclusion i An additional operating period of 30 days at 75% power is justified for j McGuire 1 on the basis that the wear rate for tubes at this power level has I
been established and that the consequences of this operation have been evaluated and found to be acceptable.
3 p pp ~ . g. ,
. . . . ~ . . . . . . . .
Page 1 of 6 McGuire Nuclear Station Results of Steam Generator ECT 3-82 7-82 11-82 b #
Row Column Supp. % TV Volume % TW Volume % TW Volume Remarks Steam Generator 'A'
- ' *C d d d d 46 50 14 O O O O 47 56 14 * * *
- 6 2E-5 47 60 14 * * * * <2 <5E-6 16 * * *
- 4 IE-5 47 61 14 0 0 4 IE-5 6 2E-5 16 * * *
- 0 0 8 4E-5 48 55 16 * - - -
6 2E-5 48 56 12 * * *
- 4 IE-5 Plugged 11-14-82 14 5 1.6E-5 9 6E-5 23 3E-3 16 6 2E-5 4 IE-5 6 2E-5 17 * - - -
10 8E-5 48 59 16 * * *
1 Page 2 of 6 3-82 7-82 11-82 Column b Row Supp. % TW' Volume % TW* Volume % TW Volume Remarks Steam Generator 'A' 48 60 11 * * *
, 19 * * *
- 4 IE-4 48 62 16 0 0 6 2E-5 8 4E-5 49 37 16 * - a a 2 SE-6 49 38 16 * * *
- e e 6 2E-5 49 41 16 * * *
- 0 0 8 4E-5 49 43 15 * * *
.49 51 19 * * *
16 * * *
- 10 8E-5 49 52 - * * * * - -
Plugged 7/4/82
. ~!
Page 3 of 6 3-82 7-82 11-82 b b Row Column Supp. % TW Volume % TW Volume % TW" Volume Remarks Steam Generator 'A' 49 54 14 * * *
- 4 IE-5 Plugged 11-14-82 12 * * *
l 1
i Page 4 of 6 I 3-82 7-82 11-82 Row Column Supp. % TV" Volume % TW Volume % TW Volume Remarks Steam Generator 'A' 49 61 11 * * *
- 4 IE-5 Plugged 11-14-82 12 *
- 0 0 49 62 10 * * * * <2 <5E-6 11 * * * * <2 <5E-6
. 12 * * *
6 2E-5 20 * * *
- 4 Page 5 of 6 i
~
3-82 7-82 11-82 Column Supp. b Row % TW* Volume % TW" Volume % TW' Volume Renarks Steam Generator 'B' 49 52 14 * * *
- 3 7E-6 17 * * * * <3 <7E-6 19 * * *
49 57 17 * * *
. Steam Generator 'C' 49 39 16 *
Page 6 of 6 .
4 3-82 7-82 11-82 b
Row Column Supp. % TW' Volume % TW" Volume % TW" Volume Remarks Steam Generator 'D' 49 74 16 *
- 9 6E-5 21 2.6E-3 17 * * *
- 8 4E-5 19 1.5E-3 17 * * *
- 7 3E-5 49 81 17 * * * '*- 12 1.6E-4
All volumes are in cubic inches C
No defect detected d
Defect detected but too small to size
" Signal noise prevented defect prediction