|
---|
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
[Table view] |
Text
__ _ . _ - - _ _ - _ _ _ _ _ _ _ _ _ - _ - _ - _ _ - _ - . - -
E; M
- .V
~
DUKE POWER GOMPANY P.O. BOX 33189 CHARLOTTE. N.C. 28942 HAL B. TUCKER retarnown
=== roses ===v , (704) 07:>+sas
=UDLEAR P=Ont OTION -
~
December 13, 1985 <
5
{ Q , N 5$1 rector Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1 Washington, D.C. 20555' Attention: B.J.-Youngblood, Director PWR Project Directorate #4 Subject - McGuire Nuclear Station Docket Numbers 50-369/370 TurbineL0verspeed Protection System; Response to Request for Information
! On' August 30, 1985, Duke' Power Company proposed Technical Specification changes relative to Turbine Overspeed Protection. By letter of October 15, 1985 (E.G.
Adensam to H.B. Tucker) the NRC staff requested additional information. Attached are the staff questions and the Duke responses to those questions.
m.
Very truly yours,
. b Hal B. Tucker ff 2O
.g SAC /jgm
~ Attachments
.cc: Dr. J.-Nelson Grace, Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 3100 Atlanta, GA 30323 W.T. Orders .
Senior Resident Inspector I McGuire Nuclear Station 1 J c-Mr. Dayne Brown, Chief Radiation Protection Branch % D *.
Division of Facility Services
- Depart' ment of Iluman Resources P.O.. Box 12200 s Raleigh, N.C. 27605 8512260089 851213 PDR ADOCK 05000069 7
P PDR c:
f-I. ,
g- ATTACHMENT I QUESTION 1:
In Attachment 11 of your submittal, you state that a study has shown that McGuire Nuclear Station has the same or very similar equipment in the TOP system as those of the Farley Nuclear Plant. Provide the study (or a suita-ble reference if publically available). Clarify (a) whether you extrapolated results from the Westinghouse evaluation and applied them to the McGuire TOP.
. system assurance program accordingly; or (b) whether the study is an indepen-dent analysis of the-McGuire TOP syctem.
RESPONSE 1:
Attachment la is a interchangeability listing of style numbers (Part Numbers) for turbine components at different stations. As can be seen on the attach-ment the major components listed in the Overspeed Reliability Program i.e.,
Throttle valves, Governor valves, Intercept valves, Reheat Stop valves and mechanical overspeed trip device are identical at McGuire and Farley. The information listed on Attachment hwas taken from the Westinghouse Steam Turbine Division Interchangeability Data Southeastern Area Utilities book.
The electronic overspeed protection circuits are basically identical since both Farley and McGuire have the Westinghouse DEH control systems.
The answer to the second portion of question (1) is (a): DPCo. extrapolated the Westinghouse results of their Farley evaluation and applied them to McGuire knowing the virtual identica1 ness of the components and control system.
QUESTION 2:
You propose certain test performance periods which deviate from the Westinghouse recommendations for Faricy. For example, Westinghouse recommended a monthly test of turbine valves whereas you propose testing every 4 months (Section 4.4 of Appendix I). You state that these deviations have been deemed appropriate for McGuire based on actual test results which indicate that the testing frequency does not need to be increased. Provide these test results and justify quantitatively the using of these test results in deriving longer periods of testing, calibration, and maintenance intervals.
, RESPONSE 28 DPCo. wishes to clarify the sentence on Attachment II, page 2, paragraph I which stated: "As indicated in Appendix I, Duke Power has deviated from certain test performance periods which Westinghouse recommended for Farley".
This should have been " Duke Power has deviated from certain maintenance periods which Westinghouse recommended for Farley". Duke Power is proposing the same maintenance periods on the throttle valves, governor valves and overspeed devices (electrical and mechanical) as Farley but are proposing more stringent maintenance periods on the intercept and reheat stop valves (40 month inspections vs. 60 month). As part of the program Duke Power will be disassembling and inspecting all turbine valves on a 40 month basis instead of
- just one (1) of each type valve every 40 months as is now required by Tech.
Spec, The deviation noted above is a deviation from the generic Westinghouse recommendations, not the approved Farley-Specific program.
Duke Power is deviating from the generic Westinghouse recommendations because the proposed inspection and maintenance schedule increases the reliability of the Overspeed Protection System. Review of the testing history reveals no problems which would have prevented proper operation of the overspeed protec-tion system.
QUESTION 3:
You state in Attachment III that "The potential insignificant increase of catas-trophic turbine failure would not have any adverse impact on the power plant safety or safety related equipment." Provide quantitative results (e.g., failure probability per year) to substantiate this statement. Compare the failure probability of the TOP system with the proposed testing intervals to the failure probability of the TOP system with the testing intervals within the standard Technical Specification.
RESPONSE 3:
The proposed increased to'st interval for the Turbine Overspeed Protection System may result in an increased failure probability for the system; which, in turn, may result in an increased probability of catastrophic turbine failure in the event of a coincident overspeed event. The potential increases have not been quantitatively analyzed. The potential for, and effects of, turbine missile generation have been analyzed and are discussed in Final Safety Analysis Report (FSAR) Sections 3.5.2.7 and 10.2.3. Safety-related equipment is protected from postulated turbine missiles by Category 1 structures. Therefore, no increase in the probability of catastrophic turbine failure will result in an adverse impact on plant safety. Turbine Overspeed Protection System failure probability as a function of test interval, like the probability of catastrophic turbine failure, is solely an economic issue not a safety issue. Therefore, a quanti-tative analysis of failure probability is not justified by any additional safety assurance.
l k_
i
^
r
.. . ATTACFtENT lo, '
INTERCHANGEABILITY LIST I SEQUENCE _15_S D LE_ NUMBER DATE 10-28-74 PAGE NO. Zg6 Q STYLE NUMBER v PART NAMC SHOP ORDER CUSTOMER PH{D INST, LEAF . F ITEM QTY. REC.
723J204003 CASING LOWER 013A003581-01 FL ORID A POWER C LIG 01-09 1250-4019 1 1 1 K CASING LOWER 013A003591-01 VA ELECTRIC PWR 01-09 1250-4019 1 1 1 K CASING LOWER 013A003931-01 VIRG[NI A ELEC PWR CD 01-09 1250-4019 1 1 1 K CASING LOWER 013A004261-01 ALABAMA POWER CD CASING LOWER 01-09 1250-4019 1 1 1 K 013 A004 351-01 DUKE POWER CD 01-09 1250-4019 1 1 1 K 723J205G04 ASSY DWG 013A003511-01 FLORIDA POWER CORP ASSY DWG 01-06 1250-4023 1 13 1 K 013 A003581- 01 FLORIGA POWER & LIG 01- 06 1250-4023 1 13 0 K ASSY_DWG 013A003591-01 VA ELECTRIC PWR 01-06 1250-4023 1 13 0 K ASSY DWG 013A003931-01 VIRGINIA ELEC PWR CD 01-06 1250-4023 1 -13 123JLQ5G09 0 K ASSY DWG 01]A004261-01.__ ALABAMA POWER CO 723J206G01 ASSY DWG 01-06 1250-4023 J __13 __0 K 013A003511-01 FLORIDA POWER CORP 01-10 1250-3620 1 62 0 K OWESEED ASSY DWG 013 A003581- 01 FLORIDA POWER & LIG 01-10 1250-3620 1 62 0 K g,g g ASSY DWG ASSY DWG 013A003591-01 VA ELECTRIC PWR 01-10 1250-3620 1 62 0 K 013A003931-01 VIRGINIA ELEC PWR CD 01-10 1250-3620 1 62 0 K ASSY DWG sw 013A009261-01 ALABAMA POWER CD 01-10 1250-3620 1 62 0 K ASSY DWG Ly> 013 A 004351-01 DUKE POWER CO 31-10 1250-3620 1 0 0 K 723J207A01 ASSY DWG 013A003511-01 FLORIDA POWER CORP 01-28 1250-3619 9 1 0 K 723J207G01 ASSY DWG 013A003581-01 FL OR ID A POWER & LIG 01-28 1250-3619 9 1 0 K ASSY DWG 013A003591-01 VA ELECTRIC PWR 01-28 1250-3619 1 9 0 K ASSY_QWG 013AQO3931-01 VIRGIMIA ELEC PWR CD 01-29 _1250-3619 1 9 0' K ASSY DWG 013 A 004351- 01 DUKE POWER CD 01-28 1250-3619 1 9 723J211G01 0 K ASSY DWG 013 A 004351- 01 DUKE POWER CD 01-10 1250-3620 1 61 0 K 723J212 A01 BEARING COMPLETE 023A003513-01 FLORIDA PGMER CORP 10-19 1250-4023 1 14 1 *K BEARING COMPLETE 023A003513-01 FLORIDA POWER CORP 10-79 1250-4023 1 14 1 *K ,
BE AR_ING_CQMLETE _02 3 AQO15_83- 01 J_ LOR 10A_P_QWE R & L LGH lQ_-19 _1250-1023 J 3 _1 *K. !
BEARING COMPLETE 023A003583-01 FLORIDA POWER & LIGH 10-79 1250-4023 1 3 1 *K' BEARING COMPLETE 023A003592-01 VA ELECTRIC PWR 10-19 1250-4023 1 3 1 *K i BEARING COMPLETE 023A003903-01 DUKE POWER CO 10-19 1250-4023 1 3 1 *K i BEARING COMPLETE 023A003903-01 DUKE POWER CO 10-79 1250-4023 1 3 1 *K ;
BEARING _ COMPLETE 0134003904-01 DUKE POWER CD 10-19 ._1250-4023 _1 3 1 *K _ !
BEARING COMPLETE 023A003904-01 OUKE POWER CO 10-79 1250-4023 1 3 1 *K i BEARING COMPLETE 023A003913-01 DUKE POWER CO 10-19 1250-4073 1 3 1 *K BEARING COMPLETE 023A003913-01 DUKE POWER CO 10-79 1250-4023 1 3 1 *K>
BEARING COMPLETE 023A003914-01 DUKE POWER CO 10-19 1250-4023 1 3 1 *K BEARING COMPLETE 023A003914-01 DUKE POWER CO 10-79 1250-4023 1 3 1 *K 8E ARING COMPLETE 023A003933-01 VIRGINIA ELEC PWR CO 10-19 1250-4023 1 3 1 *K BEARING COMPLETE 023A003933-01 VIRGINIA ELEC PWR CO 10-79 1250-4023 1 3 1 *K '
BEARING COMPLETE 023A004263-01 ALABAMA POWER CO 10-19 1250-4023 1 3 1 *K i BEARING COMPLETE 023A004263-01 ALABAMA POWER CD 10-79 1250-4023 1 3 1 *K
_72 3J212GOL m . ASSY OWG 0234003903-01 DUKE POWER CO 1.0-79 1_250-4.023 _1 13 0 K, ,
INTERCHANGEABILITY LIST .-
SEQUENGE_I5_ STYLE _NUM8ER DATE [Q-2g-74 PAGE _NO. h93; j STYLE NUMBER v PART NAME - SHOP ORDER CUSTOMER PH-CD INST. LEAF F ITEM QTY. ' RE 4571D81G01 VALVE 013A004261-01 ALA8AMA POWER CD 39-10 1250-4018 1 30 1
- i i dWH9 hat dk'o4[ ASSY DWG 013A004351-01 DUKE POWER CO 39-10 1250-4018 1 53 0 4571085001 INSERT 013A003511-01 FLORIDA POWER CORP 39-10 1250-4018 1 10 1 INSERT 013A003581-01 FLORIDA POWER E LIG 39-10 1250-4018 1 10 1
- J INSERT 013 A003 591- 01 VA ELECTRIC PWR 39-10 1250-4018 1 10 1 *
- INSERT RING 013A003931-01 VIRGINIA ELEC.PWR CD 39-10 1250-4018 1 to 2
- l INSERT 013A004261-01 ALABAMA POWER CO 39-10 1250-4018 1 10 1 *
, INSERT 013A004351-01 DUKE POWER CO 39-10 1250-4018 1 10 1 *
! 4571D87G01 80DY 013A003283-01 GEORGI A POWER COMPAN 04-41 1250-3802 1 45 1 j BODY 013 A003 5 LL-Q1 FLOR LD A POWER CORP 04-41 1250-4001 J __1h i j BODY 013 A003511- 01 FLORIDA POWER CORP 04-42 1250-4006 1 58 1 i BODY 013A003581-01 FLORIDA POWER C'LIG 04-41 1250-4005 1 58 1
] BODY 013A003581-01 FLORIDA POWER G LIG 04-42 1250-4006 1 58 1 j BODY 4
013A003591-01 VA ELECTRIC PWR 04-41 1250-4005 1 58 1 BODY 013A003591-01 VA ELECTRIC PWR _04-42 1250-4006 J 58 1 BODY 013A003931-01 VIRGINIA ELEC PWR CD 04-39 1250-4007 1 53 1 i DUMP VALVE BODY 013A003931-01 VIRGINIA ELEC PWR CD 04-42 1250-4179 3 5 2
) BODY , 013A004261-01 ALABAMA POWER CD 04-39 1250-4007 1 53 1 DUMP VALVE BODY 013A004261-01 ALABAMA POWER CD 04-42 1250-4179 3 5 1 j BODY O LJ A004351-01_ DUKE _ POWER CD 04-39 1250-400lj 53 2
} BODY 013 A004351-01 DUKE POWER CD 04-40 1250-4008 1 39 2 1 DUMP VALVE BODY 013 A004351- 01 DUKE POWER CO 04-42 1250-4179 3 5 3 2
4571090001 STEM 013A003511-01 FLORIDA POWER CORP 39-10 1250-4018 1 29 1
- I STEM 013A003581-01 FLORIDA POWER & LIG 39-10 1250-4018 1 29 1 *-
l STEM _013 A003 591-01 VA ELECTRIC PWR 39-10 J 2 50-4018 1 29 1 *C i STEM 013A003931-01 VIRGINIA ELEC PWR CD 39-10 1250-4018 1 29 2 C 1 STEM 013A004261-01 ALABAMA POWER CO 39-10 1250-4018 1 29 1 C STEM VALVE 013A004351-01 DUKE POWER CO 39-10 1250-4018 1 29 1 0 4571092001 BUSHING 013A003511-01 FLORIDA POWER CORP 39-10 1250-4018 1 14 1 *C
, BUJHING 013 A0035_81- 01. FLORIDA POWER E_L_I G 39-10 1250-40_18 J _14 1 *C i BUSHING 013A003931-01 VIRGINIA ELEC PWR CO 39-10 1250-4018 1 14 2 *C
- BUSHING 013A004261-01 ALABAMA POWER CO 39-10 1250-4'18 1 14 1 *C l 4571092002 BUSHING 013A003591-01 VA ELECTRIC PWR 39-10 1250-4018 1 14 1 *C i 4571P92002 BUSHING 013A004351-01 DUKE POWER CO 39-10 1250-4018 1 14 1 *C
} 4572D26079 STUD DWL #3 013A004221-01 SAVANNAH ELEC & PWR 09-18 718J-0797 1 1 1 *D 4572040211 STUD DWL HOLE #5.32 013A003521-01 MI SSI SSI PPI PWR EL 10-13 724J-0745 l' 1 2 *Q 4
4572D50079 STUD 6, 66 013A004232-01 FLDREDA POWER & LIGH 10-13 7930-0678 1 6 2 *k STUD 6, 66 013A004232-01 FLORIDA POWER C LIGH 10-13 793D-0678 1 6 2 *M
. 4572D50085 STUD DWL HOLE #4 013A003280-01 GULF POWER COMPANY 10-13 683J-0467 1 1 1 *K ST.UD_DWL 4 013A003831-01 TAMPA _ ELECTRIC _CO 1_0- 13_6 83_J-0 467 1 1 1 *k 5
l
INTERCHANGEABILITY LIST ,
, T .N .
SEQ 4ENCE IS_SLYLE_NW8ER 57Ytf NUMBER tf PARV NAME DATE ~
LO-28-J4 PAGE_ 2472' SHOP ORDER CUSTOMER PH {D 725J437023 GSKT 65.25X60.00X.06 01 INST. LE AF F ltEM ' GTV. REC '
GSKT 65.25X60.00X.060!T 013A003902-01 ~ DUKE POWER CE. E~03 I2iO5060 1 725J437031 013A003912-01 DUKE POWER CO 5 '2 IK~
GSKT 71.00X60.00X.06 01 013A003902-01 OUKE POWER CO.
61-00 1250-5000 1 5 2 *K
-325J437032 GSK T 71. 00X60.00X.060li 013A003912-01 DUKE P0wER CO 61-00 1250-5000 1 10 4 *K:
GSKT 9 7. 50X 8 8. 2 5 X.06 01 - 013A0039Q2:Q1 DUKE POWER CO.
61-00 1250-5000 1 10 4 *K 725J587G01 GSKY 97.50X88.25X.060IT 013A003912-01 DUKE POWER CO 61-00 1250-5QQQ 1 11 2 *K BONNET 013A003511-01 FLDRIDA POWER CORP 61-00 1250-5000 1 11 2 *K BONNET 013A003581-01 FLORIDA 40-10 1250-4017 1 35 1 K SONNET 013 A003591-01 VA ELECTRIC PWR POWER & LIG 40-10 1250-4017 1 35 1 K BONNET 40-10 013A003931-03 VIRGINIA ELEC PWR CD 39-10 1250-4017 1 1250-4017 1 35 2 K BONNET 35 2 725J614G01 013A004261-01 ALABAMA POWER CO K
ASSY DWG 013A003581-01 FL OR ID A 40-10 1250-4017 1 35 2 K 725J660GO7 ASSY DWG 013A003581-01 FLORIDA POWER & LIG 22-00 725J-0357 1 POWER E LIG 18 0 K ASSY DWG 013A003591-01 VA ELECTRIC PWR 32-00 725J-0357 1 18 0 *K
.455Y_DMG 18-01 1250-4010 1 12 0 K 725J 732G01 ASSY DWG 013A003531-01 _VA_ ELECTRIC P_WR 1.8 _03_1250-4010 l_ 0 013A003511-01 FLDRID A POWER CORP 13 K_
77yggg4 ASSY DWG 013 A003591-01 VA ELECTRIC PWR 40-10 1250-4017 1 57 0 K g4ggg ASSY DWG 40-10 1250-4017 1 58 0 ASSY DWG 013A003931-01 VIRGINIA ELEC PWR CD 39-10 1250-4017 1 K 013A004261-01 ALA8AMA POWER CO 58 0 K
_IZ5JJ_32GQ6 ASSLDWG 40-10 1250-4017 1 58 0 K 725J761G01 ASSY DWG 013_AQD4351- 01_RUKE_P_0WER_C_0 39-10J 250-4017 J 0 0 K ASSY DWG 013A003511-01 FLDRIDA POWER CORP 01-28 1250-3619 1 10 013A003581-01 FL OR IDA POWER C LIG 01-28 0 K ASSY DWG 013A003591-01 VA ELECTRIC PWR 1250-3619 1 10 0 K ASSY DWG 013A003931-01 01-28 1250-3619 1 to 0 K 4SiLDWG VIRGINIA ELEC PWR CD 01-29 1250-3619 1 10 0 K 725J761G03 ASSY DWG 013A00h351-01 JUKE _P_0WEILCO 725J800A03 013A004261-01 ALABAMA POWER CD 01:28 3250:3619_1._l0 0 __ E_
BRG ALT FOR T/C 01-28 1250-3619 1 0 0 013A003523-01 MISSISSIPPI PWR &L 10-79 K ASSY DWG 013 A003523-01 MISSISSIPPI PWR & L 10-79 1250-4055 1 13 0 K 8RG ALT FOR T/C 013A003524-01 MISSISSIPPI PWR EL 10-79 1250-4055 1 14 Og K ASSY DWG
_013 A Q0_3_524- 01 1250-4055 1 13' O K 725J815G04 ASSY DWG MI SSI11] PPI PWR E,L _10-79J 250-4 Q15 _1 14 0 725J819A03 013 A003832-01 TAMPA ELECTRIC CD' 06-00 K
ASSY DWG 013A003524-01 M ISSI SSI PPI PWR & L 10-19 1250-3022 1 8 0 K 8RG ALT FOR T/C 013A003524- 01 MISSISSIPPI PWR &L 10-19 1250-4055 1 14 0 K 725J819008 BEARING UPP 1250-4055 1 13 0
$ _725J819009 SE ARING LOW 013A003524-01 MISSISSIPPI PWR & I. 10-19 1250-4055 1 K 013A003524-01 3 1 K
! 725J823G01 ASSY DWG ' MI SSI SSIPPI PWR &L 10-19 1250-4055 1 5 i
ASSY DWG 013 A003882-01 SOUTH CAROLINA ELEC 18-03 1250-3742 1 1 K 013A003882-01 22 0 K l ASSY DWG SOUTH CAROLINA ELEC 18-06 1250-3742 -1 22 0 725J823G02 ASSEM8LY DWG 013A003883-01 SOUTH CAROLINA ELEC 18-06 1250-3742 1 K 013 A003883-01 22 0 K 725J823_G16 CASE _UPR SOUTH CAROLINA ELEC 18-03 1250-3742 1 23 0 013AQO3883-01 K SOUTH _ CAROLINA _ELEC_ 38-03 l250:3742_ 1 3 1 K
e.
~
" INTERCHANGEABILITY' LIST
'o'*
- SEQUENCE _IS_SLYLE NUMBliR l ..
.[
DeTE__10-28g74 PAGE NO
]363 _
STYLE NUMBER v PART NAME SHOP ORDER CUSTOMER PH-CD ' INST. LEAF - F ITEM QT Y. REC.
732J744G09 ASSY DWG 013A004001-01 GULF POWER 732J757GOL 41-10 1250-4110 1 38 0 K
, ASSY DWG 013 A 004001- 01 GULF POWER 19-39 1250-2935 1 732J759G01 ASSY DWG 7 .0 K-013A003931-01 VIRGINIA ELEC PWR CD 19-39 1250-4012 1 3 0 K i 732J759GO4 ASSY DWG 013A 003 591-01 732J761G01 VA ELECTRIC PWR 19-39 1250-4012 1 4 'O K ASSY DWG 013A003931-01 732J761G04 VIRGINIA ELEC-PWR CO 19-39 _1250_4312 _1 4 _,_ _Q K ASSY DWG 013A003591-01 VA ELECTRIC PWR I
732J770G01 19-39 1250-4012 1 5 0 K ASSY DWG 023A003903-01 DUKE POWER CD 732J779G01 07-02 1250-2848 1 17 0 K ASSY DWG 023A003904-0I ASSY DWG DUKE POWER CO 07-02 1250-3654 1 9 0 K.
023A003914-01 DUKE POWER CO 07-02 1250-3654 1 8 0 K 132J812G01 ASSY DWG 013A003931-01 VIRGINIA ELEC PWR CO 42-10 1250-4153 J ASSY DWG 74 0 K S#USE##T 013 A003931-01 VIRGINIA ELEC PWR CD 41-10 1250-4267 1 74 0 K.
ASSY DWG 013A004261-01 ALABAMA POWER CO l $4Lv6 ~ 41-10 1250-4153 1 74 'O K-ASSY DWG 013A004261-01 ALABAMA POWER CO 42-10 1250-4267 1 74 0 K ASSY DWG 013 A 0043 51- 01 DUKE. POWER Cd j 41-10 1250-4153 1 74 0 K i ASSY OWG Ql)10_0_i3_51 01 _DJKJ P0wER CO i
732J813001 YOKE 42-1_0 _L2J0-426_7 _1. 0 0 K 013 A003 931-01 VIpdINIA ELEC PWR CD 42-10 1250-4153 1 7 2 K' l YOLK, SUPPORT v13A003931-01 VidoINIA ELEC PWR CO 41-10 1250-4267 1 7 2 K
{ YOKE 013A304261-01 ALADA9A POWER CD 41-10 1250-4153 1 7 1 K j YOLK SUPPORT 411A004261-01 ALA3AVA POWER C3 42-10 1250-4267 1 T 1 K j YnKE 313 A_0043 51 - 0: QuKF POWE4 CJ i
YOLK SUPPORT 41-13 1250-4153 l' T. 3 K 013 A 004351-01 DUKE POWER CO 42-10 1250-4267 1 7 3 K
- T32J827001 CYLINDER 013A003931-01 VIRGINIA ELEC PWR CD 04-41 1250-4154 2 HYDR AULI C CYL 45 2 *K 013 A003931- 01 VIRGINIA ELEC PWR CD 04-42 1250-4179 2 45 2 K CYLINDER .
} HYDRAULIC CYL
( 013A004261-01 ALABAMA POWER CD 04-41 1250-4154 2 45 1 *K 1 013A004261-01 _ ALABAMA POWER CD 04-42 1250-4179 2 45 1 *K j CYLINDER 013 A 0043 51- 01 DUKE POWER CD HYDRAULIC CYL 04-41 1250-4154 2 45 3 *K
] 013 A0043 51- 01 DUKE POWER CD 04-42 1250-4179 2 45 3 *K i 732J828G01 ASSY DWG 013A003931-01 VIRGINIA ELEC PWR CO 41-34 4
ASSY DWG 1250-3617 1 19 0 K '
.J6eM54r 013A003931-01 VIRGINIA ELEC PWR CO 42-34 57pe_/XW'8 ASSY_QWG 01]A00_i26L-01.
1250-3677 1 19 0 K
_ ALABAMA PQWER CO 41-34 _115_0-3677 1 19 0 K i ASSY DWG 013A004261-01 ALABAMA POWER CD ASSY DWG 42-34 1250-3677 1 19 0 K 013 A0043 51- 01 DUKE POWER CO 41-34 1250-3677 1 0 0 K a
ASSY DWG 013A004351-01 DUKE POWER CO j 732JC29G01 ASSY DWG 42-34 1250-3677 1 0 0 K !
013A003881-01 SOUTH CAROLINA ELEC 19-39 1250-2935 1 6 0 K j 732J960G01 ASSY DWG 013A003912-01 DUKE POWER CO 07-02 1250-2950 1 4 0 K
- 732J 976G01 ASSY DWG 013A004232-01 FLOR ID A POWER C LIGH 21-00 732J-0976 1 0 0 K ASSY DWG 013A004232-01 FLORIDA POWER E LIGH 21-00 732J976G04 ASSY DWG 732J-0976 1 0 0 K 1 013A004232-01 FLORIDA POWER & LIGH 21-00 732J-0976 1 37 0 K i ASSY DWG 013A004232-01 i FLORIDA POWER & LIGH 21-00 732J-0976 1 37 0 K j _733 J_00__8GO.1__ _ AS SY_DWG ,_02.3 A 003901- 01 i
DUKE PDWER_C0 ._10_-10_1250-4194 _1__6.2 ,0. . K, !