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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
. .
Dime Pown COMPANY Powza Btm.nzwo 422 SorTa Carmen SrazzT, Cnimmirz. N. C. asa4a w i l.LI A M C. PA R M E R. .J R.
vice*=more January 18, 1980 ts. .-o c. A.c. 7o.
S et.= ** nowcwo= 373-4082 Mr. Harold R. Denton, Director Office of Nuclear React'or Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Attention: Mr. Robert L. Baer, Chief Light Water Reactor Project Branch No. 2 Re: McGuire Nuclear Station Units 1 and 2 Docket Nos. 50-369, 50-370
Dear Mr. Denton:
The purpose of this letter is to. respond to the request for information trans-mitted by Mr. Robert L. Baer's letter of October 15, 1979. The response to Question 1 (tabular information) addresses only Class 1E equipment located inside containment; equipment outside containment will be addressed in sub-sequent submittals. It should also be noted that this information super-cedes previously submitted information concerning the qualification of Westinghouse supplied transmitters and RTD's located inside containment (W. O. Parker letters to Harold R. Denton dated November 20, 1978 and August 31, 1979).
~
Enclosed are: .
r4vCT T E;lym[ddsrse t{ Rect 2edy Inf oBhd - ?:.2 . . _ . _ . . .ranmenta Qualificatier c' r' - ir ~_m.u Gen ac:.cn ouu Rc ~ d m1 Ecuipment
^ --
~~-&--.~..__ . . . - - - - - - - . - __
- 2. Five (5) copies of Pesconse to Request for Information Concerning Environmental Qualification of Class 1E Instrumentation and Electrical Equipment
% v,.nr.-4 n f - _ _ _ _ ___ __-- _ _ _ -
Also enclosed is:
- 1. One (1) copy of Application for Withholding, CAW-79-45 (Non-Proprietarv) .
1794 120 p . ~e,%
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g 2 % pocI Anniversary a
SE $
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% 8 0 () 1 '? 4 0 907 l
Mr. Harold R. Denton, Director
'anuary J 18, 1980 Page Two As this submittal contains information proprietary to Westinghouse Electric Corporation, it is supported by an affidavit signed by Westinghouse, the owners of the information. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.790 of the Commission's regulations.
Accordingly, it is respectfully requested that the information which is pro-prietary to Westinghouse be withheld from public disclosure in accordance with 10CFR Section 2.790 of the Commission's regulations. Correspondence with respect to the proprietary aspects of this application for withholding or the supporting Westinghouse affidavit should reference CAW-79-45, and should be addressed to R. A. Wiese= ann, Manager, Regulatory and Legislative Af fairs, Westinghouse Electric Corporation, P.O. Box 355, Pittsburgh, Penn-sylvania 15230.
Ve ; truly yours, /
/
. /
/ <
/Qu- <b-/ 6 William O. Parker, Jr.
GAC/sch Attachments 1794 121
McGuire Nuclear Station Response to NRC Request for Information Concerning Environmental Qualification of Class 1E Instrumentation and Electrical Equipment Ouestion 1:
The FSAR Tables that identify the operational requirements of equipment which .
must function during and subsequent to the design basis accidents are general and do not provide sufficient information for the review of equipment quali-fication. Therefore, provide a table listing of all Class 1E safety-related equipment and appropriate qualification related data for each as noted in the attachment. This table should include all equipment located both inside and outside of containment, including balance-of-plant and nuclear steam system supplied equipment.
Where components have been qualified by an equipment system test, identification of the equipment is sufficient, i.e., individual components need not be listed.
Equipment components should be identified where qualified by separate tests or analysis. Where more than one item of a given type is used, it is only nec-essary to present the required information for one representative item of that type for the worst case environment.
For equipment located outside containment which may not have been qualified to abnormal environmental conditions, the environmental design requirements for this equipment should be provided and noted as such in column 5. For each area of the plant where such equipment is located the normal operating extremes in environmental conditions should be provided and noted as such in column 4. A footnote should be provided for each such area to provide the basis that the normal operating extremes in environmental conditions will not be exceeded. Such basis should include the quality of environmental control systems, their redundancy, sources of power and cooling, and operating require-ments to maintain suitable environmental conditions during all modes of plant operation. The monitoring of environmental conditions in such areas and of the eq uipment controlling such environments should also be addressed to provide assurance that such conditions are maintained.
Response
See attached table and notes for Class IE equipment located inside containment.
Question 2:
IEEE Std. 323-1971 does not specifically address aging mechanisms as a consid-eration in the qualification of safety-related electrical equipment. Subsequently, IEEE Std. 323-1974 addressed aging in the sequence of factors to be considered.
While for many components, aging may not play a significant role in the ability of a component to withstand the effects of an abnormal or accident environment and still perform its required function; there are certain materials which may be subjected to degradation over a long period of time. It is the staff's position that applicants with qualification programs for safety-related electrical equipment, conducted in accordance with IEEE Std. 323-1971, should undertake an investigation of the electrical equipment to ensure that significant aging mechanisms do not exist which could invalidate the conclusions of prior cualifi-cation. Sources of information, specifically material manufacturers data, should 1794 122
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_2-be consulted as a part of this review. Therefore, you are requested to conduct such an evaluation and to report your findings at the earliest opportunity. For any equipment for which significant aging mechanisms are identified, provide the justification and time interval for acceptable use of this equipment which does not invalidate its prior qualification or provide other proposed alternatives such as requalification or replacement with qualified equipment and not subject to aging concerns.
Response
Duke Power Company will evaluate the in-containment Class lE equijment for signi-ficant aging mechanisms. While only limited data is available on specific materials utilized in this equipment, actual in-service experience with equip-ment of this type has not demonstrated significant aging mechanisms. However, we will investigate the in-containment Class lE equipment and report at the time of discovery any equipment for which significant aging mechanisms are identified including the justification for cintinued use and/or reasonable alternative action. This on-going investigation will necessarily be very time consuming and will rely heavily on EPRI research, NRC studies, NPRDS information, IE Bulletins and Circulars, and industry research and testing.
1794 123
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g g StPMARY OF (NVIROPMf MTAL QUAL 1FSCATION OF CLA55 If EQUIPMENT N "~P' i*'Y LOCATED INSIDE CONTAINMENT M
f QUlPMf NI MO6EL OR ACCGDINI (flVIR0lM(N T OPE RAB ILIIV OPERA 88LITY ACCURACY ACCURACY b QUALIFICAllDN IDiNIlflCAllON MANUFACTURf R IOthTIFICAll0N E NVIPONM( NT 10 WHICH RIQUIRED lN D(MONS TRAIE D REQUIRED DEMONSTRATED R(POPI ANb (t) NtiMaf R (2) QuA L IF l(D ACCIDfMI M[TH00 E NVI RONME N T ()) (% of Span) (% of Span) (4) a,b,( a,b.c Transmitter -
Pressurlier Pressure Barton
[(Lot)4 1)
Temp: 327 F c Press: 14.8 psig Temp:
Press' St Initlation $ minutes post DOE 1 10% ( ] NS-TMA-1950 Anderson to Stola (McGulee ' snit 1) RH: 8001 6 RH:
Rad: Ja10 R Rad: _ _ NS-TMA-2120 Chee Spray: N/A Chee Spray: Boric Anderson to 5tola acid and sodlum hydrsulde soln. Method: Test a,b,c ~
Transeltter - Sarton ( )**** Temp: 327 F Tow:
~
St Initiation Nota $ 1 10% Nota $ Nota $
Pressurlier Pressure (Lot 2) Press: 14.8 psig Press.
(McGuire Unit 2) RH: 10M 6 RH:
Rad: 3:10 R Rad: ,. _
Chen Spraj: N/A Chem Spray: Boric acid and sodlum hydromide soln.
- g a,b.c~ e,b.c Transmitter -
Pressur lier Level Barton ( ) Teep: 327 F Teg:
~
2 eseeks 4 months g 25%
NS-TMA-1950 (Lot 1) P re s s : 14.8 psig Press: post D8t post DitE Anderson to stola (McGuire Unit 1) RN: 10M 7 RH:
Red: 3ml0 R Rad: . _ N5-TMA-2120 Chen Spray: Boric Chee Sprey: Boric Anderson to stola acid and sodlum acid and sodlum tetraborate soln. hydromide soln. Method: Test a,b c~
Trans=ltter -
Pressur iser Level Barton ( **' Temp: 327 F Press; 14.8 psig Temp:
2 s,eeks Note 5 ~+ 25% Note 5 Note 5 (Lot ) Press: post DOE (McGuire Unit 2) RN: 100% RH:
Red: 3ml0 R Rad: . .
Chem Spray: Boric Chee Spray: Boric acid and sodlum acid and sodium tetraborate soln. hydroxide soln a,b,c transmitter -
5/G Level (NR)
Barton ( )*** Temp: }27 F Teep:
~
Reactor trip 4 months Trip Function: a,b.c ps-TMA-1950 Press: 14.8 psig (Lot 1) Press: plus k months post DBE 1 10% ($ min) Anderson to 5tola (McGuire Unit 1) RH: 100% RH: post DBE 7
Rad: $ml0 R R.d: - ~ PAM Function-. NG-TMA-2120 Chem Spray: Boric Chem Spray: Borec Anderson to stola acid and sodlum 1 25% (4 mo) .
acid anJ sodium _
tetraborate soln. hydromide soin. Method: Test f
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====* MCGulRE NUCLEAR STAit0N Page 2 p')
SUMMARY
OF ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT Revision 0
- LOCATED INSIDE CONI AlNMENT Non-Proprietary i O ,
I fQUIPM(NI MODEL OR ACCIDENT E NVI R04tE N T OPi hA81 LlTY OPfRABILITY ACCURACY AC CUMCY QUALIF8 CAT 10N BOE Nilf lC All0N MANUFACTURfA S DE NilF ICAT ION ENVB NMENT TO WHICH REQ'ilRED IN DEMONSIRATED RfQUIRED DEMONS T RAIE D REPOPT ANO gg) Ntris E R QuALIFIE D ACCIDENT METH00 ENVIRONNENT (3) (% of Span) (% of Span) (4) a.c a,b.c
~
T ransmi t te r - Barton ( ) Temp: 327 F P re s s: 14.8 pslg Temp: Reactor irly Note 5 Trip Function: Note 5 Note $
5/G tevel (NA) (Lot 2) Press: plus 4 mont%s 1 10% (5 min)
(McGuire Unit 2) RH: 100% RH: post DBE Rad: 5=10 7R Rad: PAM Function:
Chem Spray: Soric Chem Sp' ray: sJric 125% (4 mo) scid and sodium acid and sodlum tetraborate soln. hydromide soln.
8
[
Transmitter -
RC5 Flow Veritrak
( ).c --- The RCS flow signal the normal containe, are not required for accidents that cause a change in nt operating envirannent, e
ac I a,b c e,b,c '
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feo year life RIO -
RCS Temperature (NR)
Rosemount Temp: 327 F Press: 14.8 pstg Temp:
Presst SI Initiation plus I hr 1 0.2% { ] WCAP 9157 and Duha letter Perkar to RN: 100%g RH: Post SLB Denton dated December
- Rad: Im10 R Red: 19, 1979 Chem Spray: N/A Chem Spray: SorlC (40 year life acid and sodlum based on rad Method: Test / Analysts hydroxide soln. ef fects only) e,c a,b.c e,b.c
~
(
~
AfD-RCS Temperature (WR)
Rosemount ) Temp: 327 F Press: 14.8 psig Tenp:
Press:
2 weeks post SLS il year life plus 100 days 1 0.2% ( ] WCAP 9157 and Duke letter Parkar to RH: 1 RH: post SLS Denton dated December Red: lato R Red: , _ 19, 1979 Chem Spray: Boric Chem Spray: Boric (Il year life acid and sodlum acid and sodlum based on rad Method: Conwarlson to tetraborate soln. hydroulde sein. effects only) Model 176 EF e,c Test / Analysis Encore Neutron Detectors (Ptn.er Range)
W IGTD
( ) The power range neui ron detectors are not required for a In the normal conta nment operatlng er vironment
.cidents that caus i e change a,b.c Electric Hydrogen W Sturtevant A Temp: ISO F Temp:
) months I year N/A N/A WCAP 7820 and Reccatilner Press: 14.8 psig Press: post DBE post D8E Supplanents 1-4 RH: 1001 g RH:
Rad: Iml0 R Rad: WCAP 7709-L and Chem Spray: Boric Chem Spray: soric Supplements 1-4 acid and sodlum acid and sodlum tetraborate soln. hydroalde soln. Method: Test i
s N}
M. W m ( f.u l p t intttAR stall 0N Page 3 g @ StevekV 0F E NVIPONMif.l AL (tat ti ll All0N OF CLASS lE (QUIPM(NI Revision 0 61 LO( A fl D lt.5 81 i LONTAlWENT Non-Proprletary s uul t ru N i .
, not'fL On A(CIDfNl t hV l R0fMI NI DPikAbillIV OPI RAl; s t i f f A(CURACY ACCURAlY QUAL t f lC Al lbN liffIfff(AllDN TURfR 1[if Nilf lCAf l0N I NV IP OPME N T 10 WHICH R[Q'llRf D $N DtMONSIRAf t D REQulRED DtMON$lkAl(D REPOP1 Auu ,
, V t!UMa t R g QuALIF11D ACCIDfNI MtlHOD
~~
INVIRONNtNT (3) gg 4
Cont a lemernt Air Joy /Re l i ance 2nF-330081 Temp: 180 F Temp: 330 F 2 months
)
I year N/A N/A Test Report FF-14282 i Ret.sen fan Motors Press: 14.8 psig Press: 85 pilg post D8E post DBE and Supplemental :
RH: 300% RH: 1 Iechnlcal Paper TA-4089' 0
It ad: In10 R Rad: 2=10 R Chem Spray: Boric Chen Spray: Boric Test Report X-604 acid and sodlum acid and sodlum tetrat, orate soin, hydroxide soln. Method: Test i
Hydrogen Sk laener Joy / Re l lence I YF-882315 Temp: 180 F Temp: 330 F 2 months 1 year N/A N/A Test Report FF-14282 l f an Motor s Press: 14.8 psig Press: 85 psig post DBE post DBE and Supplemental RH: 100% RH: 100% Technical paper TA-4081l Rad; tal0 0R Rad: 2a10 0 I Chem Spray: Boric Chem Spray: Boric Test Report X-604 acid and sodium acid and sodium tetraborate soln, hydro =Ide soln. Method: Test ,
i Valve Mutoe Operators Rot or k 7 NAI, il NAl, Tes:,,: 327 F Temp: 340 F variable - 30 days N/A N/A Test Report Nll/4 h 14 NAl, 16 NAl, Press: 14.8 psig Press: 75 psig 10 sec to 30 post DBE Deceneer 1970 30 NAI, 40 NAl, RH. l00% RH: 100% days post DBE g
/0 NAl, 90 NAl Rad: Inl0 0 R Rad: 0 2 s 10 R Test Report IRll6 Chem Spray: Boric Chem Spray: Boric October 1973 acid and sodium acid and sodium te traborate soln, hydroxide soln. Method: Test Valve Motor Operators Limitorque SM8 Temp: 327 F Temp: 340 F variable - 30 days N/A N/A Test Report: 600-376-A Press: 14.8 psig Press: 105 psig to sec to 30 post DBE September 1972 RH: 100% RH: 100%g days post D8E Red: inl0 0 R Rad: 2ml0 Test Report: 600-456 Chen Spray: Boric Chem Spray: Boric December 1975 acid and sodium acid and sodium tetraborate soin. hydroxide soin. Metbed: Test Valve Solenold Oper at ors valcor V70900-Jl-1 Temp: 327 F Temp: 346 F Operate upon 31 days N/A N/A Test Report V70900-21-3 Press: 14.8 psig Press: 833 psig receipt of 50 post D8E QR70900-21-1 RH: 1001 RH: 100g signal Rad: 1x10 7R Rad: 2ml0 R Method: Test them Spray: N/A Chem Spray: Boric acid and sodium hydronlde soln.
1
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SUMMARY
OF [NVIRONM1NI AL QUAllF l(' i l0N OF C LASS 11 (QUlPME NT Revision 0 LOC Al[D IN51LL (' ' I AIPN!NT Non-Proprietary N
IQuilHiN1 Molet L 04 At e lbl NI ( NV I ROIN[ N T OPikAhlll1Y OPfRA84 Lily A C( URAC Y ACCURACY QUAL IF I C Al l(.N l IbihillitAllON MA :'ef ACluRf R IDtNilflCAll0N f fJVil Dia11NT 10 WHICH RIQ'llRf D IN Dt NON51 pal (D RfQUIRED Ot MON 51 RA1(D hi t-O*1 AIJb (1) UtHtit R (2) QUAL lF ilD ACClDENI ML 10 (NVIRONMENT (3)
C oe.t e l eme nt Air Ret ur n Rotork llMAll Temp: 180 F Temp: 340 F 5 min (men) 30 days N/A N/A Test Report Nil /4 isolat ion Danipe r Motor Press: 14.8 psig Press: 75 psig post 08E post 08E Decenteer 1970 RH:
Rad:
LOOT 7 la10 R RH:
Rad:
1%
2x10 R Test Report TRil6 Chem 5 pray: Boric Chem Spray: Soric October 1973 ac1d and sodlum acid and sodlum tetraborate soln. hydroxide soln. Method: Test Dif ferential Pressure Solon 7PilADW Temp: 180 F bitch f or Danipe r Press: 14.8 psi 9 Conteel RH: 100% hte: This device is presently under92ing e'wironmental quellfication tesi ing. Results of th : testing l Red: Iml0 IR are expected to t.e available in mid-February 1980 l Chem Spray: Boric 1 acid and sodlum i tetraborate soln.
Electrical Peeetrations D.G. O'Br ien Types A,B,C. Temp: 327 F Temp: 340 F 4 months 4 months N/A N/A Test Reports ER-247.
D.E.F,G.H,J, Press: 14.8 psig Press: 15 psig Post DBE post DBE tR-252, and E R-227 K,t.M. and RH; 100% RH: 100%,0 cathodic pro- Rad: Iml0 0R Rad: 2ml0 R Method: Test / Analysis tection pene- Chem Spray: Boric Chem Spray: Boric tratton acid and sodium acid and sodlum (Note 6) tetraborate soln. hydroxide soln.
(Note ?)
C able - Okoni t e EP insulation Temp: 327 F Temp: 345 F 30 days 130 days N/A N/A Test Reports FN-l,
[untrol, Ins t rinnent e- Press: 14.8 psig Press: 104 psig Post D8E post D8E N-l, G-3, IIOE, and tlun, and 2 KV power RH: 100% RH: 10 441 Rad: Iml0 R Rad: 2m R Chem Spray: Boric Chem Spray: Boric Method: Test acid and sodium acid and sodlum tetraborate soln. hydromide soln.
Cab le - Anasonda EP insulation Temp: 327 F Temp: 346 F ) months 4 months N/A N/A Test Reports F-C4350-2 Cont r ol and 2KV puwer and Press: 14.8 psig Press; 113 psig post DBE post DBE and F-C4350 -3,and (P/Hypalon RH: 10018 RH: 100%j Supplement insulation Rad: IslO R Rad: 2mlu'R Chem Spray: Boric Chen Spray: Boric Method: Test acid and sodlum acid and sodium tetraborate soln. hydroxide soln.
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D g j MCGutRE NUCL E AR stall 0N
' Page 5 f <J P*. F r OF [ NV IRONMENI AL QUAllF t( All0N OF CLA5S DE EQUIPMENT Revision 0 N LOCATED IN5101 CONTAINME NT Non-Proprietary C
e Que s na hl Mont t Oit A(( ILi tt i INVIRONMENT OPikAblLIIV OPIRA81Ll1Y AC C URAC V ACLIJ8tACV QUAllFICAlle,N eDil i f f IC AllM HArmf AC10Hf h Ibt id i l F I cal l0N ll;Vif 0::'tt h! 10 WHICH RE Q'llR(D IN D(MONSTRAl(D RfQUlPED DE MONST RATE D kil'oet Atab ggg e isiBi m (2) QUALIFitD ACCID (NI MillN)D INVIRONME NT (3) l (4) g
(.ble - Brand Rem XLPE Insulation Teg: 327 F Temp: 346 F 30 days 30 days N/A N/A Test Report F-C4113 Control Press: 14.8 psig Press: 113 psig post DBE post 08E RH:
Rad:
10g lal0 R RH: 1007, Method: Test Rad: 2ml0 R Ctem Spray: Boric Chem Spray: Boric acid anJ sodium acid and sodless tetraborate soln. hydromide soln.
Cable- Samue l Moore EP/Hypelon Temp: 327 F Temp: 340 F s 4 months Note 8 N/A I ns t ruaent at ion N/A Test Report F-C3683 insulation Press: 14.8 psig Press: 105 psig post DBE RH: RH: 100%
100%g Method: Test RaJ: SalO R Red: 2=100R Chem Spray: Soric Ctem Spray: Boric aclJ and sodlues acid and sodlum tetratorate soin. hydroalde soln.
C ab le Terminattun/ RayCten WL5F-N Tesp: 327 F T emp: 357 F 4 months 4 months 5pilce Material N/A N/A Test Report s F-C4033-3 Sleeves and Press: 14.8 psig Press: 70 psig Post 08E post 08E B re akou t s and 11100 RH: 1001 RH: 1 Rad: i=100R Rad: 2x10 R Method: Te st / Analysis Chem Spray: Boric Chem Spray: Boric acid and sodlian acid and sodium tetraborate soln. hydroxide soln.
5 tem-Mounted t.imit Newco EA 180 Teg: 327 F Temp: 340 F 30 days (man) 30 days 5 Itches N/A N/A Namco Test Reports EA 740 Press: 14.8 psig Press: 63 psig post 08E post DBE dated March 3,1978 RH: 100% RH: 100%
Inl00R and February 22, 1979 kad: Red: 2x100R Chem Spray: Boric Chem Spray: Boric acid and sodium Method: Test acIJ and sodium tetraburate soln, hydroxide soin.
Seal Material for 3M Scotch Cast 9 Temp: 321 F Temp: 340 F 30 days Ceble Intsam.e Fittings 30 days N/A N/A Test Report 44390-1, (NR-5240) Press: 14.8 psig Press: 15 psig post DBE post DBE Rev. 4 Into 5 tem-Mounted RH: 1001 Limit Switches log RH:
Rad: Im10 R Rad: 2ml00R Method: Te st/ Analysis Ctem Spray: Boric Chem Spray: Boric acid and sodlum acid and sodlum tetraborate soln. hydroxide soln.
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Cueit e l<=ent Pressure Berton 358 Temp: 327 F Temp: 340 F 3 months 3 aunth Note 10 Note 10 Test Report 43904-l 5ensors (fransaltters Press- 14.8 psig Press: 20 psig post 08E post 00E for ti.ese signals are RH: 1001 sl H . 100% Method: Test /Analysi s located outside Rad: Isl0 7R Red: 2al0 0R c ue.t e l,.=nt ) Chem Spray: Soric Chen Spray:Nute 9 acid and sudium tetretrorate soln.
%) we Sulenoid Asco NP8316E34f Temp: 327F Temp: 346F Operate upon 30 days N/A N/A Test Report ope r at ue s NP8316E36E Press: 14.8 psig Press: llo psig receipt of post 08E AQS21678/TR RH: 100% RH: I $1 signal Rad: Inl0 7R Rad: 2x10 R Method: Test Chem Spray: N/A Chem Spray- Boric acid and sadium hydroaldo soln.
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1 of 2 Revision 0 McGuire Nuclear Station Environmental Qualification of Class lE Equipment Located Inside Containment Note 1 All equipment identified in this table is located inside the containment, specifically in the lower compartment except for the electric hydrogen recombiner, containment air return fan motors, hydrogen skimmer fan motors, containment air return isolation damper motors, differential pressure switches for damper control and cables associated with these devices which are located in the upper compartment.
Note 2 The parameters that compose the overall worst-case containment accident environment are as follows: .
Temperature (Upper Compartment): 180F peak; time history as shown in FSAR Figure 6.2.1-24 (Rev 36)
Temperature (Lower Compartment): 327F peak; time history as shown in FSAR Figure (LATER-to be provided in FSAR Revision 39)
Pressure (Upper and Lower Compartment): 14.8 psig peak; time history as shown in FSAR Figure 6.2.1-23 (Rev. 36)
Relative Humidity: 100%
Radiation: Total integrated radiation dose for the equipment location includes 40 year normal operating dose plus the appropriate accident dose (except for the narrow-range and wide-range RTD's).
Chemical Spray: Boric acid and sodium tetraborate spray resulting from mixing in the containment sump of borated water from the RWST and sodium tetraborate solution from ice bed melt.
Note 3 Equipment operability requirements in the containment accident environment are as identified in FSAR Table 3.11.1-1 (Rev. 25).
Note 4 Environnental qualification test reports for the following equipment have previously been submitted to the NRC Staff:
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2 of 2 Revision 0 Transmitters-Barton (by Westinghouse)
RTD's-Rosemount (by Westinghouse)
Electric Hydrogen Recombiner (by Westinghouse)
Containment Air Return Fan Motors (by Duke)
Hydrogen Skinner Fan Motors (by Duke)
- Solenoid Operators-Valcor (by Duke)
Electric Penetrations (by Duke) -
Cable Termination / Splice Material (by Duke)
. Stem-Mounted Limit Switches (by Duke)
Cable Entrance Seal Material (by Duke)
Note 5 Qualification tests for the Barton Lot 2 transmitters have been completed, and the results are being compiled by Westinghouse into a report for submittal to the NRC Staff.
Note 6 -
Electric penetration types B,C,F, G and K are the only penetraticns required to function electrically in the containment accident environment. All electric penetrations, however, are designed and qualified to maintain their mechanical integrity under normal and postulated accident environmental condi tions .
Note 7 The McGuire electric penetrations are protected from direct spray impinge-ment by galvanized steel boxes.
Note 8 This item is being pursued with the cable manufacturer. We will report our findings in a future revision to this table.
Note 9 The containment pressure sensor devices are made of stainless steel and therefore not degraded by chemical spray.
Note 10 The containment pressure sensors and associated transmitters were qualified as a system. The overall accuracy requirement for the sensor / transmitter combination is +0%, -10% of span. The demonstrated accuracy of this combination during testing was within the accuracy requirements.
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