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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
[Table view] |
Text
, -,
DUKE Powsu COMPANY ;
Powru Dunwmo 422 Sourn Cnuncu Star.zT, CiuawrTE, N. C. 28242 l
W I L LI And O. PA R pt E R, J R.
v.cr Persiogut TELcpwo=r. Anta 704 Setase Paocauctio. July 26, 1982 373-4o 3 Mr. liarold 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 Nos. 50-369, 50-370 Control of Ileavy Loads, NUREG-0612
Dear Mr. Denton:
Please find enclosed four copies of the drawings and one copy of the report provided as information as requested in Sections 2.1 and 2.3 of Enclosure 3 of the December 22, 1980 generic letter concerning NUREG-0612. This report specifically covers the reactor buildings.
~
Ve truly yours,
, s AC _ lo William O. Parker, w
Jr.
RWO/php Attachment I cc: (w/o attachment) O}'
Mr. James P. O'Reilly, Regional Administrator j U. S. Nuclear Regulatory Commission Region II d 101 Marietta Street, Suite 3100 g T ,
Atlanta, Georgia 30303 U.S" ' -
Mr. P. R. Bemis h@
g',
NRC Resident Inspector 9,.uj McGuire Nuclear Station $@D VS w (,3) 8208030458 820726 PDR ADOCK 05000369 P PDR
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. s l :
1 McGUIRE NUCLEAR STATION 7
Reactor Building .
Control of Heavy Loads NUREG-0612 .
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I NTRODUCTION The information presented in this report is the result of a detailed evaluation of load handling systems as requested by the NRC in their letter dated December 22, 1980 concerning NUREG-0612, " Control of Heavy Loads at Nuclear Power Plants".
Scope This report is divided into two (2) parts. "Part A" addresses -
specific requirements set forth in Section 2.1 of Enclosure 3 to the NRC's letter as they pertain to the Reactor Buildings at McGui re Nuclear Station. "Part B" addresses specific re-quirements set forth in Section 2.3 of the same enclosure.
PART A Initial Review .
Crane / Load List ,
A list containing all load handling systems and their respective loads was compiled and compared to the Reactor Building General Arrangement drawings by station personnel in order to verify that the drawings correctly represented "as-built conditions".
Conditiens of Operation For the purpose of our review we broke the operating conditions in the Reactor Buildings down into four conditions.
Condi tion 1 (Full or Reduced Power)
During th!s condition the reactor is in operation. All
, vi tal systems are requi red.
Condition 2 (Hot Shutdown)
In this condition the reactor has been shut down but the reactor coolant system is pressurized above 300 psig and its temperature remains above 200*F.
~
During this condition all vital systems arc requiied. ,
Condition 3 (Cold-Shutdown, Fuel Loaded)
In this condition the reactor is completely shut down and the reactor coolant system depressurized allowing removal of the reactor head. Fuel is present in the core. During this condi tion only decay heat removal systems are needed.
9 n .--- ._. _ . . - , . .. .. . , . ._. _ . .
y
7 Condition 4 ( Cold Shutdown, Fuel Unloaded)
This condition is identical to Condition 3 except no fuel is present in the vessel. No vital systems are required.
Review of Load Handling Systems Used During Different Conditions Of Operation Condition 1 & Condi tion 2 During these conditions miscellaneous hoists are used for minor repai r work or for obtaining cold-shutdo vn but do not handle heavy loads. Operation of the Polar Crane is restricted as specified in Station Directive 3.3.6,
" Reactor Building Polar Crane and Auxiliary Hoist Operation". '
Underdrce conditions a heavy load drop can not occur precluding the need to investigate further the load handling systems or operations during these conditions.
Condition 3
. During this condition all load handling systems are subject to use. All load handling systems will be reviewed.
Condition 4 A heavy load drop during this condition would have no impact on the station since the Unit is down with the fuel unloaded and out of the building. For this reason it will not be necessary to review load handling systems and op-erations during this condition.
Based on this review, only load handling operations during Condition 3 requi re further investigation.
Development of Load Drop Areas Load drop areas were developed for each load handling system used during Condi tion 3 as shown on the attached General Arrangement drawings. The load drop area of all cranes was defined as the area over which the hook may pass if trolley and bridge travel were unrestricted. All load drop areas include an allowance for load shape and are projected to the. basement.
Locating Vital Systems in the Load Drop Areas
" Vital Systems" defined as those systems necessary for safe shutdown and/or decay heat removal, located within the load drop areas were identi fied and superimposed on the General Arrangement drawings.
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= ure ' + *Pe>M- 9 e-. _ - . ._ M
r x Load Handlinq Systems to Receive Further Consideration The IIst of load handling systems with their respective loads was reviewed to determine which systems handle heavy loads (1500 lbs. or more) .during Condition 3 The relevant drawings were then reviewed to determine which cranes or hoists handling heavy loads also contained vital systems and/or the reactor vessel in their load drop areas. These systems received further evaluation. The renaining systems were eliminated from consideration as insignficant.
Summary of Initial Review Table i summarizes the results of the initial review of load handling systems in the Reactor Buildings. This Table identifies cranes and hoists handling heavy loads during cold shutdown and indicates i f vital systems and/or the reactor vessel is located within thei r load drop areas.
Final Review
~
Scope The load handling systems identified'in Table I as handling heavy loads over vital systems and/or the reactor vessel at cold shutdown were rev;cwed for compliance with Section 2.1.3 of Enclosure 3 to the NRC's letter dated December 22, 1980 concerni ng NUREG-0612. The results of that review are described in the following sections and summarized in Table ll.
l
! Safe Load Paths Safe Load Paths are explained in Table 11. Station Directive 3.3 7, Handling of Heavy Loads,- has been impicmented to explain l the purpose of these paths.
i Establishment of Load Handlino Operations Table 11 was prepared for each load handling system which is located over vital systems and/or the reactor vessel and summarizes j
l the information requested in Sections 2.1-3c through 2.1-39 The l
table is self-explanatory.
Conclusion The initial review of load handling systems in the Reactor Buildings revealed a total of 31 cranes which handle heavy loads over vi tal systems and/or the reactor vessel . Further investi-ation of these systems showed that they comply fully with all parts of Section 2.1-3 of Enclosure 3
'All information requested under Section '2.1 of Enclosure 3 for i the Reactor Buildings is included in this report.
~ - ----W ,. --=.-2 = a-""h 4 e e, -
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i 9 PART B
, Crane / Load Combinations Considered ,
Cranes considered for this review are those operational during Condition 3 of the plant and identi fied in Table i of this report under the heading " Handles Heavy Loads and has Reactor Vessel in Load Drop Area". The associated loads are found in Table ll of this same report.
Postulated Load Drops Only two (2) of the crane / load canbinations possible while the Unit is at cold shutdown will be considered because they envelope the others. ,
- 1. The first accident consists of dropping the reactor head onto the vessel flange. This accident could cause structural damage to the vessel and attached piping resulting in loss of cooling pater. (Criteria lil)
- 2. The second accident consistsof an oblique drop of the reactor head onto the upper' internals. This accident I could damage fuel, releasing radioactive gases (Criteria
- 1) and result in increased gap activity above acceptable limits. (Criteria ll)
These analyses are scheduled to be completed in September of thi s yea r'. The results will be forwarded to you at that time.
4 a
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. TABLE I
' Reactor Building .
f
. _.~ ' Cold' Shutdown (Fuel Loaded) r Handles Heavy Handles Heavy Loads and Has Loads and Has Does Not Vital Equipment Reactor Vessel Vital Equipment Reactor Vessel
/ Not Located In in Load Drop in Load Drop
, , ~' Handle Heavy ' Not Located in r Crane or Hoist 'G.A. No. Loads' ' Loa ~d Drop Area " Load Drop Area '
' ' Area Area Non-Existent R001 & -
1 R024 Non-Existent R002 &
R025 -
3 ,
Non-Existent R003 & , g
-/
R032
( .
Al VL Fan Motor R004 & '
/
f Monorail R031 ,
R005 & / / -
VL Fan Motor 1 Monorail R030 Pipe Chase R006 & . /- /
Monorail R028
, Pipe Chase R007 & / /
- ! Monorail R027 I
l Non-Existent R008 & .
- R026 Hon-Existent R009 & . .
R033 ;
Manipulator R010 &'- /
Crane R034 T e 6 kl *
((
~ -
~ TABLE I
[' .
t
[ ..
' ' Reactor' Building .
- Cold' Shutdown (Fuel Loaded)
N Handles Heavy Handles Heavy
[ Loads and Has Loads and Has y Does Not Vital Equipment Reactor Vessel Vital Equipment Reactor Vtssel i , Handle Heavy Not Located in Not Located In in Load Drop in Load Crop Crane or Hoist 'G;A;'Noe Loads' *'L'oad Drop Area ' Load ~ Drop Area Area Area
! Manipulator R011 & / , /
Crane Aux. R035 j Poist non-Existent- R012 .
Non-Existent R013 f .
Pipe Chase R014 & *
/ /
Jib Crane R036 -
Reactor R315 & . / / -
Coolant Pump R039 Jib Crane
~
n, Reactor R016 & / / , '
Coolant Pump R037 Jib Crane l- .
i Reactor R017 & / /
l Coolant Pump R042 .
Jib Crane Control Rod Drive R018 & ~ -
/ /
< Mechanism Jib R041 -
Crane .
i . .
a .
. TABLE I
Reactor' Building
. ' Cold Shutdown (Fuel Loaded) . . .
Handles Heavy Handles Heavy Loads and Has Loads and Has .
Does Not Vital. Equipment . Reactor Vessel Vital Equipment Reactor Vessel
, Handle Heavy Not Located in Not Located In in Load Drop in Load Drop Crane or Hoist 'G.A.'No. Loads L'oa'd Drop Area ' ' Load Drop Area ' Area Area Reactor Coolant R019 & / /
~
Pump Jib Crane R040 Reactor Equip. R020 & -
/ /
Access D.cor R038
- Jib Crana Polar Crane R021 & ,/ /
R043 Polar Crane R022 & / . /
Aux. Hoist R044 .
Ice Condenser R023 & / /
Bridge Crane R045
~
~
tiiscellaneous R029 / /
Equipment - -
Monorail
. e i
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" + - ,_
TABLE 11 'L . . ,
Crane or Hoist: V L Fan Motor Monorail .
General Arrangement No: R004, R005, R030. R031
'ComoIfances .
trane Inscection . . ,
ANSI 830.2-1976, Ch. 2-2i Yes
. Crane Desien CMAA Spec. 70: (1)
ANSI 830.2-1976, Ch. 2-1: (1) .
Ocerator Trainino . .
ANSI B30.2-1976: yes .
Cor.pliance Safe Load Paths is Movement Governed by a Procedures Lifting to ANSI &
Located Painted Described (Lbs) in Load Handling For Deviation Device NUREG 0612 Load on G.A. ,on Floor Frcr SLP7 Used Soecs.
Veicht Dwas. *at Plant Procedures Procedure?
Load Yes *(2) (5) Yes V L Fan Motor 2,400 (2) '(2) (2)
Yes (2) (5) Yes i Misc. Equip. <4,000 (2) (2) (2)
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.' 's TABLE 11 L ,
Crane or Hoist: " Pipe' Chase' Monorail ,,
3 General Arrangement Wo: R006, R007, R027,'R028 -
Capacity: 2 Ton -
Come!Iances Crane insoection At S t S30.2-1976, ch. 2-2: Yes .
Crane Desicn cMAA Spec. 70: (1) . .
AtJSI S30.2-1976, ch. 2-1: (1) - ,
4 Occrator Traininc -
A!!S3 B30.2-1976: Yes .
is Movement Conoliance Safe Load Paths Lifting to AftSt &
. Painted Described Governed by a Procedures (t.bs) Located For Deviation Device NUREG 0612 Leal on G.A. on Floor in load Handling Used Soccs.
Procedures Procedure? Fre - SLP?
i Load Vei c ht Dwgs. ~ at Plant (5) Yes (2)' (2) Yes ~ -(2)
Misc. Equip. <4,M0 (2)
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TABLE !! .
(
} Crane or Holst: Manipulator Crane (Reactor Cavity) .
j I General Arrangement No: R010, R034 f ' '
Capacity: 2 Ton
'Comoliances .
gl Crane insoection ,
ANSI S30.2-1976 Ch. 2-2: yes
. Crane Desien i CMAA Spec. 70: Yes . '.
1 '
i ANSI B30.2-1976, Ch. 2-1: Not specifically qtated in specifications ,
1 a
Ocerator Trainino i.; ,
ANSI B30.2-1976: Yes ,
I is Movement Compliance 1
Safe Load Paths Lifting to ANSI &
i Painted Described -Governed by a Procedures
' (Lbs.) Located Load Handling For Deviation Device NUREG 06.12 ,
Load on G.A. on Floor in Specs.
Procedure? Fron SLP7 Used 1 Load Veicht Dwas. 'at Plant Procedures
'N/A Air actuated gripper Fuel Assembly 1,500 N/A N/A N/A Yes' is integral part to
.t crane mast
.i N/A N/A Yes N/A
- Control Rod , Clusters 93 -
N/A ,
(RCC) e
+
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TABLE 11 E .
Crane or Holst: Manipulater Crane Auxiliary Hoist +-
General Arrangement No: R0ll, R035
$ Capacity: 1 Ton i
Cc: oliances
. Crane Desien .
2 CMAA Spec. 70: Yes - -
/
ANSI B30.2-1976, Ch. 2-1: Not s'ecifically p stated in'spbcifications " ,
Ooerator Trainino ,
ANSI B30.2-1976: Yes .
Compliance Safe Load Paths is Movement Governed by a Procedures Li f ting to ANSI &
(Lbs) Located Painted Described load Handling For Deviation Device NUREG 0612 j
Load on G.A. on Floor in Used Specs.
at Plant Procedures Procedure? Fren SLP7 1 Load Veicht Dwas.
.N/A (5) Yes N/A N/A Yes -
Stud Tensioners
< N/A N/A (5) Yes N/A Yes Misc. Equip. < N/A N/A O
6 O
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.< TABLE'll Crane or Hot 5t: Pipe ChasP, Jib Crane ,
General Arrangement No: R014. R036
- Capacity: 5 Ton Como Iances 1
i Crane insoection ' * .
b Af!Si B30.2-1976, Ch. 2-2: Yes
) . Crane Desien C.".AA Spec. 70: (1)
ANSI B30.2-1976, Ch. 2-1: (1) , . . ,
Ooerator TrainInc
Compliance Safe Load Paths 15 Movement Governed by a Procedures lifting to ANSI &
(Lbs.) Located Painted Described NUREG 0612 in L'oad Handling For Deviation' Device Load on G.A. on Floor Frcr SLP? Used Soecs.
Veicht Dwas. at Plant Procedures Procedure?
Load
' (3) (5) Yes j Misc. Equip. < 10,000 (3) (3) (3) Yes i
o .
Q_ _-
TABLE !!
Crana or Holst: Reactor Coolant Pump Jib Crane- .
General Arrangement No: R0i5, R016, R017, R019, R037, R039, -R040, R042 .
I -
Capacity: 3 Ton Comoliances_
) ,
l Crane insoection -
I ANSI 330.2-1976, ch. 2-2: Yes i Crane Desien o
,j CMAA Spec. 70: (l) . ,,
ANSI B30.2-1976. Ch. 2-1: (1) . .
he
}
j ooerator Traintne .
Yes .
ANSI 330.2-1976: .
i; Comoliance Safe Load Paths is Movement Governed by a Procedures Lifting to ANSI &
(Lbs) Located Painted -Described Device NUREG 0612 l
on Floor in 1. cad Handling For Deviation Load on G.A. Frc - SLP7 Used Specs.
Dwas. at Plant Procedures Procedure?
Load Veicht __
(5) Yes (3) Yes - (3) h Misc. Equip. <6,000 (3) (3) b .
~
1
. . 1 e
I 1
6 k._______
~L *
) TABLE 11 O ' .
Crana or Hoist: Control Rod Drive Mechanism Jib Crane . .
+
s General Arrangement No: R018. R041 .
~ '
capacity: 3 Ton ,
ccmoliances ,
l -
Crane Insoection , .
J AMS! S30.2-1976, ch. 2-2: Yes .
Crane Design CMAA Spec. 70: (1 ) - .
Ansi B30.2-1976,, ch. 2-1: (1) , , , "
Ceerator Trainino . .
ANSI 330.2-1976: Yes .
is Movernent Coroliance Safe Load Patns Procedures Lifting to ANSI f.
Painted Described Governed by a (1.bs) Located For Deviation Device NUREG 0612 on Ficor in l'oad Handling Load on G.A. Frer SLP? Used Soecs.
Dwas. at Plant Procedures Procedure?
Load L'e i c h t Yes (3) (5) Yes Control Rod (3) (3) (3)
<6,000 Drive Mechanism .
. . . . s 1 . .
? .
w _
TABLE II .
trane or Moist: Reactor Equipment Access Door Jib Crane , .
General Arrangement ?;o: R020, R038 .
~
Ca;:aci ty: 15 Ton Cc-ofiances Cra-e Inscection ,,
A :s 330.2-1976, Ch. 2-2: Yes .
Crane Desicn ,
C.".AA Spec. 70: (1) _ _
ANSI S30.2-1976, Ch. 2-1: (1) , , , -
Doerator Trainine .
ANs! 530.2-1976: Yes .
Compliance Safe Load Paths is Movernent to ANSI r, Governed by a Procedures Lifting Located Painted Described Device NUREG 0612 on Floor L'oad Handling For Deviation (Lbs) oad on G.A. in Procedure? Frcr SLP? Used Soces.
k'e i cht Dwas. at Plant Procedures Load
~ .
(3) (5) Yes Misc. Equip. <30,000 (3) (3) (3) Ye's i .
1 . ...
l . , .
+
U, . . .
TABLE 11 's - .
- trane or Hoist
Polar trace ', ,
General Arrangement flo: R021, R043 .
capacity: 175 Ton compliances trane insoection .. ,
Anst 330.2-1976, ch. 2-2: Yes Crane Desien c.MAA spec. 70: Yes ,-
ANSI S30.2-1976, Ch. 2-1: Yes . . . ,
Doerator T.ainina-ANs1 330.2-1o76: Yes Compliance Safe Load Paths is Movernent Governed by a Procedures Li f ring to ANSI &
Located Painted Described (lbs) in Load Handling For Deviation Device NUP.EG 0612
'l Load on G.A. 'on Floor Frcr SLP? Used Specs.
Dwes. at Plant Procedures Procedure?
k*eicht
.L.o. a d Recctor Vessel Head 100,000 (6) (6)' (6) 'Yes' ('6 ) Yes (7)
Reactor Coolant Pump 55,200 (6) (6) (6) Yes (6) Yes (7)
(7)
Yes (6) Yes RCP Motor 88,300 (6) (6) (6) Yes Missle Shields 160,000 (6) (6) (6) Yes (6) Yes -
, Pressurizer
- (rlooded Weight) 307,828 (6). (6) , (6) -
Yes ,
. .(6) (5) - Yes .
k o
LI
.4 . . . .
} -
c
- c. -
..I
~
" TABLE II t7
~ .
Crane or Hoist: Polar Crane. Auxiliary Hoist ,
General /.rrangement No:
R022, R044 .
~- -
T' -
Capacity: 25 Ton ,
cc oliances trane insoection ,
AMsl 330.2-1976, Ch. 2-2: Yes .
Crane Design CMAA Spec. 70: Yes ANSI S30.2-1976, Ch. 2-1: Yes . . . ,
Goera:or Traininc .
Yes ANSI 330.2-1976:
Compliance Sare Load Paths is Novement Governed by a Procedures Lifting to ANSI f.
(Lbs) Located Painted Described. Device NUREG 0612 on G.A. on Floor in l'oad Handling For Deviation Load Frc- SLP? Used Seces.
Veicht Dwas. at Plant Procedures Procedure?
Load s . .
36,000. (6) (6) (6) Yes (6) (5) Yes RCP Hatch Yes (6) (5) Yes Misc. Equip. <50,000 (6) (6) (6) ,
6 l .
\ -
L _
~ ~~
TABLE'fI .
~
~ ~~ ~
Crane or Meist: Ice C'endenser Bridge Crane .
General Arrargement No: R023, R045 -
Capacity; '3 Ton .
a Cc-cliances Crane insoection .
AMSI 330.2-1o76, Ch. 2-2: Yes
~
Crane Desieg . .
C."AA Spec. 70: See Note . .
ANSI B30.2-1976, Ch. 2-1: See Note ,, , ,
coerator Trainina ,
ANSI 330.2-1976: Yes ., , ,
Compliance
- Safe Load Paths is Moverunt (IDS) Described Governed by a Procedures Lifting to ANSI &
Located Painted Device NUREG 0612 Load on G.A. on Floor in load Handling For Deviation Procedures Procedure?- Fre- SLP? Used Soces.
Lead Veics.: Dwas. at Plant
~ . .
Ice Condenser Yes Equipment <6,000 (4) (4) ,
(4) Yes (4) (5) t Note: Crane designed to Electric Overhead Crane Institute Specification f61. ,
e .
\ .
's .
TABLE 11 ~.
Miscellageous Equipment Monorail Crane or Heist: - .
General Arrangement !!o: R029 -
2 Ton .' .
Capacity:
Comoliances Crane insoection .
Anst 330.2-1976, ch. 2-2: Yes Crane Desien - .
CMAA spec. 70- (l) . .
ANst 330.2-1976, ch. 2-1: (1) . . . ,
Operator Trainine '
Yes .
ANS! 330.2-1976:
- Co.oliance sar'e Load Paths is Movement to ANsl r, Governed by a Procedures Lifting (Lbs) Located Painted Described Device NUP.EG r612 on Floor in l'oad Handling For Deviation load on G.A. Frc-- SLP7 Used specs.
Dwas. at Plant Procedures Procedure?
Load k'e i cht Yes ' {2) (5) Yes (2)'
Misc. Equipment <4,000 (2) (2)
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(1) These specifications do not apply to the design of monorails or jib cranes.
Our monorails and jib crancs are designed in accordance with the applicable AISC code and/or OSHA Code of Federal Regulations, Part 1910.179.
(2) The safe load path of a monorail can only be the vertical projection of the monorail on the underlying floor. For this reason, it is unnecessary to perform this work. .
(3) The safe load paths for these jib cranes can only be the vertical projec-tion of the radius of curvature on the underlying floor since the radius
' of curvature produces only one set path for egiupment that is being lifted.
For this reason, it is unnecessary to perform this work.
(4) There will be no safe load paths for this crane due to it requiring access to all parts of the Ice Condensers. For this reason, it is unnecessary to perform this work.
(5) The lifting device used in handling these loads consist of the appropriate size and number of chain-falls, chokers, and slings as determined by the rigger.
In making his selection, the rigger draws on his experience and the Ele-mentary and Advanced Rigger Training provided at the Duke Power Company Training Center. Choker and sling sizing is determined by the estimated weight of the load. If additional information is needed, the Riggers Hand-
' book is used. All lifts are made by qualified people who, by experience
. and/or training are cognizant in the movement of loads.
-(6) Each equipment load listed for the polar crane has a specific storage point. The polar crane will lower the equipment to the same point each time. For this reason, it is unnecessary to perform this work.
(7) The investigation of these special lifting devices is proceeding. The
_ results will be forwarded to you when the investigation is complete.
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