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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N3901999-10-25025 October 1999 Advises That Info Provided in & Affidavit Re Holtec Position Paper WS-115,rev 1,repts HI-87113, Rev 0,HI-87114,rev 0,HI-87102 Rev 0 & HI-87112,rev 0,marked Proprietary,Will Be Withheld from Public Disclosure ML20217L8591999-10-21021 October 1999 Discusses 990921 Request for Approval to Perform Alternative Testing as Part of Vermont Yankee Nuclear Power Station IST Program.Informs That Submittal Reviewed Against ASME Code Section XI Requirements & Forwards Safety Evaluation ML20217M1181999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20217D9711999-10-13013 October 1999 Responds to Request That Information Titled Addl Info Re Cycle Specific SLMCPR for Vermont Yankee Cycle 21 Be Withheld from Public Disclosure.Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20217F1261999-10-12012 October 1999 Forwards Update to Previously Submitted RELAP5 Analytical Assumptions for App R,Re RAI of 961104 BVY-99-130, Provides Clarification of Method for Determining MSIV Maximum & Minimum Pathway at Vermont Yankee Nuclear Power Station1999-10-0808 October 1999 Provides Clarification of Method for Determining MSIV Maximum & Minimum Pathway at Vermont Yankee Nuclear Power Station ML20217C1501999-10-0707 October 1999 Forwards Insp Rept 50-271/99-11 on 990809-27.No Violations Noted.Insp Focused on Effectiveness of Engineering Functions in Providing for Safe Operation of Plant BVY-99-128, Submits Listed Addl Info in Support of 990414 Request for Clarification to SER Confirming Adequacy of Space Cooling for HPCI & RCIC Sys,Re Item II.K.3.24 of NUREG-0737.Copy of NEDE-24955,encl1999-10-0606 October 1999 Submits Listed Addl Info in Support of 990414 Request for Clarification to SER Confirming Adequacy of Space Cooling for HPCI & RCIC Sys,Re Item II.K.3.24 of NUREG-0737.Copy of NEDE-24955,encl ML20212J7891999-10-0404 October 1999 Informs That Licensee 980804,0628,29 & 990921 Responses to GL 98-01, Y2K Readiness of Computer Sys at NPPs Acceptable.Nrc Consider Subj GL to Be Closed for Plant ML20212J6501999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of VYNPS on 990913. No New Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues & Insp Plan Through Mar 2000 Encl ML20216J3531999-09-29029 September 1999 Responds to NRC Re Violations Noted in Insp Rept 50-271/99-12 on 990628-0811.Corrective Actions:Based on RFO 20 Maint Rule Outage Performance Review,Task Was Generated to Clarify & Enhance SD Monitoring Process BVY-99-122, Notifies of Intention to Reinstate Original Version of App F in FSAR & Correct Docket Re Assumption That Electrical Power Sys Are Designed IAW Requirements of GDC-171999-09-28028 September 1999 Notifies of Intention to Reinstate Original Version of App F in FSAR & Correct Docket Re Assumption That Electrical Power Sys Are Designed IAW Requirements of GDC-17 BVY-99-114, Provides Notification That Licensee Completed Y2K Remediation Efforts Described in Util 990608 Response to NRC GL 98-01,Suppl 11999-09-21021 September 1999 Provides Notification That Licensee Completed Y2K Remediation Efforts Described in Util 990608 Response to NRC GL 98-01,Suppl 1 BVY-99-113, Requests Approval to Perform Alternative Testing to That Specified by ASME Boiler & Pressure Vessel Code,Section XI & Asme/Ansi OM, Operation & Maint of Nuclear Power Plants. Attachment 1 Provides Justification for Alternative Testing1999-09-21021 September 1999 Requests Approval to Perform Alternative Testing to That Specified by ASME Boiler & Pressure Vessel Code,Section XI & Asme/Ansi OM, Operation & Maint of Nuclear Power Plants. Attachment 1 Provides Justification for Alternative Testing BVY-99-116, Informs of Determination That Wh Schulze,License SOP-10528-1,will No Longer Maintain License at Facility. Termination of License Requested1999-09-21021 September 1999 Informs of Determination That Wh Schulze,License SOP-10528-1,will No Longer Maintain License at Facility. Termination of License Requested BVY-99-121, Requests Extension Until 990929 to Respond to Violations Noted in Insp Rept 50-271/99-12,dtd 990819.Licensee Did Not Receive Rept Until 990830 & Addl Time Is Needed to Prepare & Allow for Adequate Review of Violation Response Submittal1999-09-20020 September 1999 Requests Extension Until 990929 to Respond to Violations Noted in Insp Rept 50-271/99-12,dtd 990819.Licensee Did Not Receive Rept Until 990830 & Addl Time Is Needed to Prepare & Allow for Adequate Review of Violation Response Submittal ML20212C1621999-09-17017 September 1999 Forwards Amend 175 to License DPR-28 & Safety Evaluation. Amend Revises TSs to Enhance Limiting Conditions for Operation & Surveillance Requirements Relating to Standby Liquid Control System BVY-99-118, Responds to RAI Concerning GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions1999-09-16016 September 1999 Responds to RAI Concerning GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions BVY-99-115, Forwards non-proprietary & Proprietary Responses to 990714 RAI Re Civil & Mechanical Engineering Considerations for Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355.Proprietary Encls Withheld1999-09-16016 September 1999 Forwards non-proprietary & Proprietary Responses to 990714 RAI Re Civil & Mechanical Engineering Considerations for Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355.Proprietary Encls Withheld ML20216F3171999-09-13013 September 1999 Forwards Insp Rept 50-271/99-06 on 990621-0801.One Violation Identified & Being Treated as Noncited Violation BVY-99-110, Informs of Util Intent to Replace Commitments Made in Licensee & Subsequently Ack in NRC with Containment Insp Criteria Defined in 10CFR50.55a(b)(2)(vi),per Drywell Coating Insp1999-08-31031 August 1999 Informs of Util Intent to Replace Commitments Made in Licensee & Subsequently Ack in NRC with Containment Insp Criteria Defined in 10CFR50.55a(b)(2)(vi),per Drywell Coating Insp BVY-99-111, Informs That Encl TS Bases Page 91 Has Been Revised to Allow Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line Uncorrected Solution & on-line 3D-Monicore Exposure Corrected Solution1999-08-31031 August 1999 Informs That Encl TS Bases Page 91 Has Been Revised to Allow Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line Uncorrected Solution & on-line 3D-Monicore Exposure Corrected Solution ML20211G4791999-08-27027 August 1999 Forwards Notice of Withdrawal of 990420 Amend Request Re TS on Reloading & Unloading Sequence of Fuel in Reactor Core When All Fuel Removed from Core BVY-99-107, Submits Response to NRC RAI Re Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355 Fuel Assemblies1999-08-26026 August 1999 Submits Response to NRC RAI Re Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355 Fuel Assemblies ML20211E8841999-08-25025 August 1999 Requests That Licensee Provide bldg-specific Justification for Use of Method A.1 at Locations Where Amplification Significantly Exceeds 1.5 Limit Above 8 Hz ML20211E1371999-08-20020 August 1999 Forwards from J Bean to H Miller & FEMA Final Exercise Rept for 990427-29 Plume Exposure & Ingestion Pathway Exercise for Vermont Yankee Nuclear Power Station.No Deficiencies Noted.Areas Requiring C/A Identified ML20211H0851999-08-19019 August 1999 Forwards Insp Rept 50-271/99-12 on 990628-0711 & Nov. Violation Re Failure to Monitor Unavailability of Specific Sys,Structures & Components During Refueling Outage Did Not Allow Adequate Assessment of Maint Effectiveness BVY-99-108, Requests That Gv Bogue,Bj Croke,Vs Ferrizzi,Me French, Bk Mcnutt,Jf Meyer & DM Navarro Take BWR Gfes of OL Exam Administered on 991006.DA Daigler & ST Brown Will Have Access to Exams Before Tests Administered1999-08-19019 August 1999 Requests That Gv Bogue,Bj Croke,Vs Ferrizzi,Me French, Bk Mcnutt,Jf Meyer & DM Navarro Take BWR Gfes of OL Exam Administered on 991006.DA Daigler & ST Brown Will Have Access to Exams Before Tests Administered BVY-99-103, Informs That Util Expects to Submit Approx Twenty Licensing Actions in FY00 & FY01,in Response to Administrative Ltr 99-021999-08-18018 August 1999 Informs That Util Expects to Submit Approx Twenty Licensing Actions in FY00 & FY01,in Response to Administrative Ltr 99-02 BVY-99-100, Forwards Revised Floor Response Spectra Diagrams,Originally Sent as Attachment 1 to Licensee to Nrc.Revised Diagrams Have More Legible Scale Markings1999-08-0202 August 1999 Forwards Revised Floor Response Spectra Diagrams,Originally Sent as Attachment 1 to Licensee to Nrc.Revised Diagrams Have More Legible Scale Markings ML20210M5791999-07-30030 July 1999 Responds to NRC 990726 Telcon Re Status of Resolution for USI A-46 Outliers.Written Summary,By Equipment Category, Listed ML20211E1701999-07-28028 July 1999 Forwards Copy of Final Exercise Rept for 990427-29,full- Participation Plume Exposure & Ingestion Pathway Exercise of Offsite Radiological Emergency Response Plans site-specific to VYNPS ML20210G5041999-07-27027 July 1999 Responds to NRC 990301 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions. Licensee Will Submit Info Re Proposed Sys Mod by 990916 ML20210J3031999-07-27027 July 1999 Submits Proposed Changes to Eals.Attachment 1 Provides Listing of Changes to EALs Along with Ref to Bases Documents Supporting Change ML20210G4271999-07-27027 July 1999 Forwards Testing Data & Associated Results for Fitness for Duty Program at Plant for 990101-0630 ML20216D7321999-07-26026 July 1999 Forwards Insp Rept 50-271/99-05 on 990510-0620.Two Viiolations Being Treated as Noncited Violations ML20209G2721999-07-14014 July 1999 Discusses Licensee Response to RAI Re GL 92-01,Rev 1,Suppl Suppl 1, Rv Structural Integrity, for Vermont Yankee Nuclear Power Station ML20209J0601999-07-14014 July 1999 Forwards Rev 11 to Vols 1-10 of State of Nh Radiological Emergency Response Plan & Vols 11-50 to Town Radiological Emergency Response Plans,In Support of Vermont Yankee & Seabrook Station.Vols 17-19 of Were Not Included ML20209G6931999-07-14014 July 1999 Forwards Request for Addl Info Re Spent Fuel Storage Capacity Expansion ML20209G1531999-07-12012 July 1999 Discusses Util Setpoint Control Program Implementation Schedule,As Committed to in Licensee 990514 Response to Notice of Violation,Insp Rept 50-271/97-10 ML20196J2321999-06-30030 June 1999 Submits Input from Util Technical Staff Re Soil Disposal on-site Under 10CFR20.2002 & Expresses Interest in Pursuing Approval to Use Same Methodology (Implemented Through Util ODCM & Reported as Noted) If Possible ML20196J7421999-06-29029 June 1999 Informs NRC That Vygs Has Implemented Severe Accident Management,As Committed to in Licensee to NRC ML20209B6111999-06-29029 June 1999 Resubmits Summary of Vynp Commitments Page to Replace Original Page Submitted with Responding to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20196J2431999-06-29029 June 1999 Informs That Author Received Call from NRR on Dirt Spreading Ltr & Questions Re Cover Ltr Statement Where Util Asks to Be Allowed to Dispose of Future Soil in Same Manner Provided Same Acceptance Criteria Met ML20209C3751999-06-28028 June 1999 Forwards non-proprietary Rev 16 to EPIP OP 3524, Emergency Actions to Ensure Initial Accountability & Security Response & Proprietary Rev 12 to EPIP OP 3531, Emergency Call-In Method. Proprietary Encl Withheld ML20209B5861999-06-28028 June 1999 Provides Alternative Y2K Readiness Status Described in Supplement 1 to GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure Rept Encl ML20196G5241999-06-22022 June 1999 Responds to Re Changes to Vermont Yankee Guard Training & Qualification Plan,Rev 8,Errata A.No NRC Approval Is Required.Encl Will Be Withheld from Public Disclosure Per 10CFR73.21 BVY-99-084, Forwards Proprietary Application & Medical Certificate for Mod of Listed SRO License,For Gj Leclair.Gj Leclair Will Be Trained & Evaluated in Accordance with Util Lsro Training Description.Proprietary Info Withheld,Per 10CFR2.7901999-06-18018 June 1999 Forwards Proprietary Application & Medical Certificate for Mod of Listed SRO License,For Gj Leclair.Gj Leclair Will Be Trained & Evaluated in Accordance with Util Lsro Training Description.Proprietary Info Withheld,Per 10CFR2.790 ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20195H1741999-06-15015 June 1999 Forwards Original & Copy of Request for Approval of Certain Indirect & Direct Transfer of License & Ownership Interests of Montaup Electric Co (Montaup) with Respect to Nuclear Facilities Described as Listed 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217F1261999-10-12012 October 1999 Forwards Update to Previously Submitted RELAP5 Analytical Assumptions for App R,Re RAI of 961104 BVY-99-130, Provides Clarification of Method for Determining MSIV Maximum & Minimum Pathway at Vermont Yankee Nuclear Power Station1999-10-0808 October 1999 Provides Clarification of Method for Determining MSIV Maximum & Minimum Pathway at Vermont Yankee Nuclear Power Station BVY-99-128, Submits Listed Addl Info in Support of 990414 Request for Clarification to SER Confirming Adequacy of Space Cooling for HPCI & RCIC Sys,Re Item II.K.3.24 of NUREG-0737.Copy of NEDE-24955,encl1999-10-0606 October 1999 Submits Listed Addl Info in Support of 990414 Request for Clarification to SER Confirming Adequacy of Space Cooling for HPCI & RCIC Sys,Re Item II.K.3.24 of NUREG-0737.Copy of NEDE-24955,encl ML20216J3531999-09-29029 September 1999 Responds to NRC Re Violations Noted in Insp Rept 50-271/99-12 on 990628-0811.Corrective Actions:Based on RFO 20 Maint Rule Outage Performance Review,Task Was Generated to Clarify & Enhance SD Monitoring Process BVY-99-122, Notifies of Intention to Reinstate Original Version of App F in FSAR & Correct Docket Re Assumption That Electrical Power Sys Are Designed IAW Requirements of GDC-171999-09-28028 September 1999 Notifies of Intention to Reinstate Original Version of App F in FSAR & Correct Docket Re Assumption That Electrical Power Sys Are Designed IAW Requirements of GDC-17 BVY-99-113, Requests Approval to Perform Alternative Testing to That Specified by ASME Boiler & Pressure Vessel Code,Section XI & Asme/Ansi OM, Operation & Maint of Nuclear Power Plants. Attachment 1 Provides Justification for Alternative Testing1999-09-21021 September 1999 Requests Approval to Perform Alternative Testing to That Specified by ASME Boiler & Pressure Vessel Code,Section XI & Asme/Ansi OM, Operation & Maint of Nuclear Power Plants. Attachment 1 Provides Justification for Alternative Testing BVY-99-114, Provides Notification That Licensee Completed Y2K Remediation Efforts Described in Util 990608 Response to NRC GL 98-01,Suppl 11999-09-21021 September 1999 Provides Notification That Licensee Completed Y2K Remediation Efforts Described in Util 990608 Response to NRC GL 98-01,Suppl 1 BVY-99-116, Informs of Determination That Wh Schulze,License SOP-10528-1,will No Longer Maintain License at Facility. Termination of License Requested1999-09-21021 September 1999 Informs of Determination That Wh Schulze,License SOP-10528-1,will No Longer Maintain License at Facility. Termination of License Requested BVY-99-121, Requests Extension Until 990929 to Respond to Violations Noted in Insp Rept 50-271/99-12,dtd 990819.Licensee Did Not Receive Rept Until 990830 & Addl Time Is Needed to Prepare & Allow for Adequate Review of Violation Response Submittal1999-09-20020 September 1999 Requests Extension Until 990929 to Respond to Violations Noted in Insp Rept 50-271/99-12,dtd 990819.Licensee Did Not Receive Rept Until 990830 & Addl Time Is Needed to Prepare & Allow for Adequate Review of Violation Response Submittal BVY-99-115, Forwards non-proprietary & Proprietary Responses to 990714 RAI Re Civil & Mechanical Engineering Considerations for Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355.Proprietary Encls Withheld1999-09-16016 September 1999 Forwards non-proprietary & Proprietary Responses to 990714 RAI Re Civil & Mechanical Engineering Considerations for Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355.Proprietary Encls Withheld BVY-99-118, Responds to RAI Concerning GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions1999-09-16016 September 1999 Responds to RAI Concerning GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions BVY-99-110, Informs of Util Intent to Replace Commitments Made in Licensee & Subsequently Ack in NRC with Containment Insp Criteria Defined in 10CFR50.55a(b)(2)(vi),per Drywell Coating Insp1999-08-31031 August 1999 Informs of Util Intent to Replace Commitments Made in Licensee & Subsequently Ack in NRC with Containment Insp Criteria Defined in 10CFR50.55a(b)(2)(vi),per Drywell Coating Insp BVY-99-111, Informs That Encl TS Bases Page 91 Has Been Revised to Allow Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line Uncorrected Solution & on-line 3D-Monicore Exposure Corrected Solution1999-08-31031 August 1999 Informs That Encl TS Bases Page 91 Has Been Revised to Allow Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line Uncorrected Solution & on-line 3D-Monicore Exposure Corrected Solution BVY-99-107, Submits Response to NRC RAI Re Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355 Fuel Assemblies1999-08-26026 August 1999 Submits Response to NRC RAI Re Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355 Fuel Assemblies BVY-99-108, Requests That Gv Bogue,Bj Croke,Vs Ferrizzi,Me French, Bk Mcnutt,Jf Meyer & DM Navarro Take BWR Gfes of OL Exam Administered on 991006.DA Daigler & ST Brown Will Have Access to Exams Before Tests Administered1999-08-19019 August 1999 Requests That Gv Bogue,Bj Croke,Vs Ferrizzi,Me French, Bk Mcnutt,Jf Meyer & DM Navarro Take BWR Gfes of OL Exam Administered on 991006.DA Daigler & ST Brown Will Have Access to Exams Before Tests Administered BVY-99-103, Informs That Util Expects to Submit Approx Twenty Licensing Actions in FY00 & FY01,in Response to Administrative Ltr 99-021999-08-18018 August 1999 Informs That Util Expects to Submit Approx Twenty Licensing Actions in FY00 & FY01,in Response to Administrative Ltr 99-02 BVY-99-100, Forwards Revised Floor Response Spectra Diagrams,Originally Sent as Attachment 1 to Licensee to Nrc.Revised Diagrams Have More Legible Scale Markings1999-08-0202 August 1999 Forwards Revised Floor Response Spectra Diagrams,Originally Sent as Attachment 1 to Licensee to Nrc.Revised Diagrams Have More Legible Scale Markings ML20210M5791999-07-30030 July 1999 Responds to NRC 990726 Telcon Re Status of Resolution for USI A-46 Outliers.Written Summary,By Equipment Category, Listed ML20211E1701999-07-28028 July 1999 Forwards Copy of Final Exercise Rept for 990427-29,full- Participation Plume Exposure & Ingestion Pathway Exercise of Offsite Radiological Emergency Response Plans site-specific to VYNPS ML20210G5041999-07-27027 July 1999 Responds to NRC 990301 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions. Licensee Will Submit Info Re Proposed Sys Mod by 990916 ML20210G4271999-07-27027 July 1999 Forwards Testing Data & Associated Results for Fitness for Duty Program at Plant for 990101-0630 ML20210J3031999-07-27027 July 1999 Submits Proposed Changes to Eals.Attachment 1 Provides Listing of Changes to EALs Along with Ref to Bases Documents Supporting Change ML20209J0601999-07-14014 July 1999 Forwards Rev 11 to Vols 1-10 of State of Nh Radiological Emergency Response Plan & Vols 11-50 to Town Radiological Emergency Response Plans,In Support of Vermont Yankee & Seabrook Station.Vols 17-19 of Were Not Included ML20209G1531999-07-12012 July 1999 Discusses Util Setpoint Control Program Implementation Schedule,As Committed to in Licensee 990514 Response to Notice of Violation,Insp Rept 50-271/97-10 ML20196J2321999-06-30030 June 1999 Submits Input from Util Technical Staff Re Soil Disposal on-site Under 10CFR20.2002 & Expresses Interest in Pursuing Approval to Use Same Methodology (Implemented Through Util ODCM & Reported as Noted) If Possible ML20209B6111999-06-29029 June 1999 Resubmits Summary of Vynp Commitments Page to Replace Original Page Submitted with Responding to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20196J7421999-06-29029 June 1999 Informs NRC That Vygs Has Implemented Severe Accident Management,As Committed to in Licensee to NRC ML20209C3751999-06-28028 June 1999 Forwards non-proprietary Rev 16 to EPIP OP 3524, Emergency Actions to Ensure Initial Accountability & Security Response & Proprietary Rev 12 to EPIP OP 3531, Emergency Call-In Method. Proprietary Encl Withheld ML20209B5861999-06-28028 June 1999 Provides Alternative Y2K Readiness Status Described in Supplement 1 to GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure Rept Encl BVY-99-084, Forwards Proprietary Application & Medical Certificate for Mod of Listed SRO License,For Gj Leclair.Gj Leclair Will Be Trained & Evaluated in Accordance with Util Lsro Training Description.Proprietary Info Withheld,Per 10CFR2.7901999-06-18018 June 1999 Forwards Proprietary Application & Medical Certificate for Mod of Listed SRO License,For Gj Leclair.Gj Leclair Will Be Trained & Evaluated in Accordance with Util Lsro Training Description.Proprietary Info Withheld,Per 10CFR2.790 ML20195H1741999-06-15015 June 1999 Forwards Original & Copy of Request for Approval of Certain Indirect & Direct Transfer of License & Ownership Interests of Montaup Electric Co (Montaup) with Respect to Nuclear Facilities Described as Listed ML20195C5891999-05-27027 May 1999 Forwards Response to NRC 990301 RAI Re GL 96-05 Program at Vermont Yankee Nuclear Power Station ML20195D5341999-05-27027 May 1999 Forwards Description of Vermont Yankees Plans for Insp of & Mods to Certain Reactor Vessel Internals BVY-99-074, Forwards Application & Medical Certificate Required for Renewal of Jd Livingston,License OP-10049,RO License.Medical Certificate Withheld1999-05-26026 May 1999 Forwards Application & Medical Certificate Required for Renewal of Jd Livingston,License OP-10049,RO License.Medical Certificate Withheld ML20195B4081999-05-24024 May 1999 Withdraws Licensee Commitment,Contained in ,To Reinitiate ITS Project Following Completion of FSAR Accuracy Verification Project.Util Will Continue to Modify Current TS with Number of Improvements BVY-99-067, Informs That Bw Metcalf,License SOP-1761-9,has Retired from VYNPS & Will No Longer Require License.Nrc Is Requested to Terminate License1999-05-21021 May 1999 Informs That Bw Metcalf,License SOP-1761-9,has Retired from VYNPS & Will No Longer Require License.Nrc Is Requested to Terminate License ML20196L1801999-05-18018 May 1999 Withdraws Licensee & Attachment,Containing Rev 2 to Vermont Yankee Operational QA Manual, from Further Consideration by Nrc.Summary of Commitments Encl ML20206K3201999-05-0707 May 1999 Forwards Response to RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML20206J2801999-04-30030 April 1999 Forwards 1998 Annual Financial Repts for CT Light & Power Co,Western Ma Electric Co,Public Svc Co of Nh,North Atlantic Energy Corp,Northeast Nuclear Energy Co & North Atlantic Energy Svc Corp,License Holders ML20206D3731999-04-27027 April 1999 Informs NRC of Changes in Recipients of NRC Docketed Correspondence ML20206B1401999-04-23023 April 1999 Forwards Replacement of Section 3(a) of NSHC Determination Provided by Re TS Proposed Change 208,suppl Section 6 ML20205S3381999-04-16016 April 1999 Submits Revised Schedule for Response to NRC 990226 RAI Re 980630 Submittal of IPEEE Rept.Info Will Be Submitted by 991231 ML20205S3891999-04-16016 April 1999 Forwards non-proprietary & Proprietary Revised Page to Holtec Rept HI-981932,supplementing TS Proposed Changed 207 Re Spent Fuel Pool Storage Capacity Expansion ML20205S3031999-04-15015 April 1999 Forwards Revised TS Bases Pages 90,227,164 & 221a,accounting for Change in Reload Analysis from Yaec to GE Methodology, Reflecting Change in Condensation Stability Design Criteria & Accounting for More Conservative Calculation ML20205P9291999-04-14014 April 1999 Requests That Rev to NRC 821029 SER for NUREG-0737,Item II.K.3.24,be Issued to Clarify Util Installed RCIC & HPCI HVAC Configuration,As Discovered During Preparation of DBDs for Sys ML20205P8191999-04-13013 April 1999 Forwards Rev 2 to COLR for Vermont Yankee Cycle 20, Dtd Feb 1999,IAW TS Section 6.7.A.4 ML20205M3191999-04-0707 April 1999 Forwards 1998 Annual Rept of Results of Individual Monitoring, Per 10CFR20.2206(b).Licensee Is Submitting Matl to Only Addressee Specified in 10CFR20.2206(c).Without Encl ML20205K0351999-03-31031 March 1999 Informs That Certain Addl Corrections Warranted for 990121 SER for Amend 163 to License DPR-28 Re Suppression Pool Water Temp.Suggested Corrections Listed ML20205K1821999-03-31031 March 1999 Informs of Modifications That Util Made to CO(2) Fire Suppression Sys,Due to Sen 188 Which Occurred at Ineel on 980728.Compensatory Actions Will Remain in Place Until Modifications Are Complete & Systems Are Returned to Svc ML20206A6951999-03-29029 March 1999 Request Confirmation That No NRC Action or Approval,Required Relative to Proposed Change in Upstream Economic Ownership of New England Power Co,Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee 1999-09-29
[Table view] |
Text
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VERMONT YANKEE l
'y ' NUCLEAR POWER CORPORATION 185 Old Ferry Road, Brattleboro, VT 05301 7002 (802) 257-5271 February 2,1999 BVY 99-21 !
1 United States Nuclear Regulatory Commission ATTN: Document ControlDesk Washington, DC 20555
Reference:
(a) Letter, VYNPC to USNRC, " Vermont Yankee Summary Report for resolution of USl A-46," BVY 96 86, dated July 1,1998 Subjeet: Vermont Yankee Nuclear Power Station License No. DPR-28 (Doeket No. 50-271)
Request for Inform < tion Renardine Resolution of USI A-46 As a result of a verbal request from the NRC staff, we are providing the attached sample evaluations for selected cable tray supports which demonstrate our use of the limited analytical review performed in accordance with the GeneralImplementation Procedure (GIP).
l l
Should you have any questions concerning this submittal, please contact Mr. Jeffrey T Meyer at i (802) 258-4105. l I
Sincerely, l
VERMONT YANKEE NUCLEAR POWER CORPORATION
/jg Gautajii4en '
Licensing Manager ;
Attachment cc USNRC Region 1 Administrator USNRC Resident Inspector-VYNPS USNRC Project Manager-VYNPS ! i Vermont Department of Public Se vice 6095 )o 1
~
9902110157 990202 i PDR ADOCK 05000271 1 P PDR _
- 5-
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l Vermont Yankee USI-A46:
Sample Evaluations for Cable Tray Deadweight Supports .;
r SQUG GIP Limited Analytical Review l
l
' This Attachment contains sample evaluations which demonstrate the use of the limited analytical review performed per Section 11.8 of the GIP. Enclosed are review Nos. 2,3,4,8, & 9 from the
" Electrical Raceway Review" Calculation. The review numbers are the same as those identified in l
Table 7-1 of the " Vermont Yankee Summary Report for Resolution of USI-A46", dated July 1,1996 l
(BVY 96-86).
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Page 1 of 25 i
. Vermont Ycnkee U:1 A46: Sansple Ev luations for Cable Tray Deadweight Cupports !
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Vermont Ycnkee USI-A46: Sample Evaluations for Cable Tray Deadweight Supports of15 SQUG CIP Limited Analytical Reviews Pcge 3
> s .
- REVIEW NUMBER 2: RB 280 SE 2
-_ CHECK DEAD LOAD:
7" e 16"]
4 Elev. 303*-6" span := 7.67 ft
, ,, w uA M
W := wt_18_66 span 78" o
W = 142.4 lb 12" w M := 2.W-(12.125 in) l
' 12-1/8" M = 3452.6 Ib in J
S A = 1.110 in'
- Check Vertical P1001: x = 0.572 in'
, := -
M o = 6.0 ksi < F b.= 25.0 ksi } MernberOK l Sx (Ref. 6.2, pg.8)
- Check 1/2" Unistrut Spring Nuts and Bolts
<F pullout := 7000.1 } Sprina nuts OK i
M Pullout := 2 W+_ Pullout = 9922*lb bolt 2 bolt arm
- Check Horizontal P1000 along ceiling:
s x_p3ooo := 0203 in' 2W Bending _ moment := 12.W.7.in - MI M 9 n n Bending _ moment = 1459.3 ib in 1
p'a 7" 16" af Page 5 CBLETRAY.MCD l
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~
. Vermont Ycnkee USI-A46: Sample Ev:luations for Cable Tray Deadweight Supports SQUG CIP Limited Analytical Reviews P ge 4 of if REQlEW ML '.
o :=
B'N m ment a = 7.2 ksi <F b = 25.0 ksi } MemberOK S x,_P1000
- Check 1/2"shellanchors:
I
t 16in I t= 376.0 lb
- Determine Allowable Load: - Anchor bolts are Phillips Red Heads
- Assume anchor bolts are adequately installed
- Cons. assume concrete strength = fc := 3000 psi PerTable C.2-1 of the GlP,1/2" expansion anchors have an allowable pullout load = Ft := 2290 lb and an allowable shearload = Fy := 2380 lb . -
Per Section C.2.7 of the GIP, the following capacity reduction factors must be used for fc = 3000 # .
RF f* RF = 0.75 RF i
+ 0.65 RF y = 0.95 P := 4000 psi P y:= tooog. psi Revised allowable loads:
F t:= F tRF F t = 1717.5 lb Fy := FyRF y Fy = 2261.0 lb } Bolts OK p
t = 0.22 < 1.0 Intarsetion Ratio.
Ft Support members and connections are OK for 1 x Dead Load 4
w/
CM.ETRAY.MCD Page 6
. ' Vermont Ycnkee UZI-A46: Sample Evaluations for Cable Tray Deadweight Suppods SQUG CIP Limited Analytical Reviews Paga F of 26
- CHECK VERTICAL CAPACITY: Per Figure 84 of the GlP the next check is a 3 x Dead Load check of the primary co'mections and the anchorage. This will be done by multiplying the previous checks by a factor of 3.
- Check connection at top:
2W + M Pullout = 2976.7 Ib Pullout := 3 (2 bolt armj The Unistrut spring nuts have an allowable load = F pullout = 2000.0 lb using a factor of safety = 3. This results in an ultimate load of F ultimate := 3-F pullout F ultimate = 6000.0 lb Factor of Scieb/ against ultimate load = FS ultimate Pullout FS ultimate = 2.02 This factor of safety against ultimate load is judged to be adequate because as the members displace under loading the puilout load will become more of a shear load and the second bolt will come more effective.
- Check 1/2" shell anchors:
f t:= 3 -" **"I +2W\
j I t= 1127.9 lb
( 16 in Interaction Ratio: b = 0.66 < 1.0 } Bolts OK Ft Support members and connections are OK for 3 x Dead Load
- The support is classified as ductile.
- The support is not a fixed-end rod hanger.
CONCLUSION: The support is seismically adequate per the analytical review guidelines of Section 8 of the GIP.
' I Page 7 C8LETRAY.WCD
.. . .w. ,
' Vermont Ycnkee USI-A46: Sample Evcluations for Cable Tray Deadweight Supports SQUG CIP Limited Analytical Reviews Pcge (o of 2T
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Vermont Ycnkee USI A46: Sample Evaluations for Cable Tray Deadweight Supports SQUG CIP Limited Analytical Reviews Page 7 of 46 AN
- REVIEW NUMBER 3: RB 280g1
- CHECK DEAD LOAD:
span := 7. A I W 1.---
oW3 W q = 107.1 Ib
[W4 W j := 3-(C 2_ inch) span
- WS W2 := span- C2 inch + C3- inch
+ C 4 inch #/,
+ 10 lbi' I
- W6 W2 = 310.8 lb W3 := span.(C 1 .5_ inch + C 2_1nch) W 3 = 60.9 lb W4 := span C 1_ inch W4 = 15.4 lb ,
W 5 := (18_25 + 10 b span .
l W 5 = 1192 lb i ft > Fireproofing = 10 lb#t for W 5 and W 6
/ i W 6 := i (18_50 + 10.lb l span + 5C 1_ inch + l 0 f Ibi ' span )
W6 = 378.6 lb 1
i Al iC .75 inch + +
/ R _ !
+ 3 A-(7 C1 .5_ inch) + -(3 A 6 C 1_ inch)
- The horizontal P1001 members are adequate oy comparison to Review #1.
- Vertical P1001 stmt is judged to be adequate. I i
CBLETRAY.MCO Page8 i
e
. Vermont Ycnkee U21 A46: Sample Evaluations for Cable Tray Deadweigil t Cupports SQUG CIP Limited Analytical Reviews Pcg3 b cf 16 b l6343
- CHECK ANCHORAGE Wj+W2+ W3+W4+W5+W6 +
punout := f 2M 4 bN 7e) pullout = 496.0 -lb <F punout = 2000.0 lb
-The embedded strut has an allet.:t:!s pullout load = F embed _ pullout := 2M -
pullout = 496.0- <F embed _pallout = 2000.0 I-
} Embed strut OK l
Support members and connechons are OK for 1 x Dead Load
- CHECK VERTICAL CAPACITY: Per Figure 8-6 of the GIP the next check is a 3 x Dead Load check of the primary connections and the anchorage. This will be done by multiplying the previous checks by a factor of 3.
pullout := 3-pullout pullout = 1488.1 lb <F pullout = 2000.0 lb } Sprina nuts OK Totalweight = 3 (W q + W2+W3+W 4+W 5 + W6) = 2976 lb
- Check Embed: The allowable capacity of 2,000 lb / ft of embed is derived using a !
Factor of Safety = 3 against the tested minimum ultimate strength. Titis F.S. car. l be reduced to 1.5 for seismic loading to be consistent with the GIP and EPRI guidelines.
Reference Attachment A.
f3\
F embed _ pullout seismic := Fembed_pulloutg 2976lb <F embed _ pullout _ seismic = 4000 Ib } Embed Strut OK M 1W F embed _ pullout _ seismic-(1.5)
- 4) Y hY FS ultimate := FS ultimate = 2.02 ,
2976- g:
Support members and connechons am OK for 3 x Dead Load
- The support is classified as ductile.
- The support is not a fixed-end rod hanger.
CONCLUSION: The support is seismically adequate per the analytical review guidelines of Section 8 of the GIP.
CBtITRAYJAc0 Page 9
" Vermont Ycnkee USI-A46: Sample Ev:luations for Cable Tray Deadweight Cupports SQUG GIP Limited Analytical Reviews Page Cl of_17__
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Vermont Ycnkee USI-A46: Sample Evaluations for Cable Tray Deadweight Cupports SQUG CIP Limited Analytical Reviews P ge 10 of.LT_
- ~. ,
I i
- REVIEW NUMBER 4: RB 280 NE 1
- CHECK DEAD LOAD:
1 18" "
UU Q $ 8 \
l 18" i
Assumeiight l W1e rmture e W2 ,
e W3 -
W light := 15 ib
= W4 I
e W5 4 l
W q := (2)-(7 A)-(C 0.75_ inch) + W light W j = 34.6 lb span := 11. A W2 := wt 18_25 span W2 = 77.3 Ib W3 := W2 W4 := W2 W5 d 18_50 span
- W 5 = 154.7 Ib
- The horizontal P1001 members are judged to be seismically adequate by comparison to Review #1. ,
1
- Vertical P1001 member is adequate by engineering judgement.
CBLETRAY.MCD Page 10 4
~ . _ _ _ _ . - . _ . . . _. . _ _ . _ . _.- ._..__._._.__._ _ _
~
Vermont Ycnkee USI A46: Sample Evaluations for Cable Tray Deadweight Cupports SQUG CIP Limitrid Analytical Reviews PCee \l of 15' l 3
' Review 44 ;
- CHECK ANCHORAGE ,
The support is secured to the ceiling by (2) Unistrut spring nuts in an embedded strut. .
Totaldeadweight= W j + W2+W3+W 4+W 5 = 421.3 ib Load is acceptable by comparison to Review #3. .t t
Support members and connections are OK for 1 x Dead Load i
Per Figure 8-6 of the GIP the next check is a 3 x Dead
- CHECK VERTICAL CAPACITY: e Load check of the primary connections and the anchorage. This will be done by multiplying thej previous checks by a factor of 3. i
- Check connection at top:
P = 1264.0 lb P := 3-(W j + W 2+W 3+W 4+W) 5 i
Load is acceptable by comparison to Review #3. i l
Suer +-1 members and contes are OK for 3 x Dead Load :
j
- Because of the brace the support may not respond in a ductde manner. Therefore it muri be 1 subjected to a lateral load check in accuide6cs with Section 8.3.4 of the GIP. l
- The lateral load check consists of subjectng the' support to a loading of 1 x dead load plus a transverse acceleration = 2.5 x floor ZPA where the raceway system is attached.
For Elevation 303' of the Resctor Building find the floor OBE E-W = ZPAOBE := 0.13 g .
- ZPA SSE = 0.26 g ZPASSE
- = 2 ZPAOBE acc = 0.65 g acc.:: 2.5 ZPA SSE i- l i
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. Vermont Yankee USI A48: Sample Evaluations for Cable Tray Deadweight Cupports SQUG ClP Limited Analytical Reviews Pzgo 12. of 18_
T E \/ isW ip4 l
Wi P q := W4 acc P q = 22.5 lbf l P 2 := W2 ace P 2 = 50.3 lbf f i
If e P 3;* W3acc P 3 = 50.3 lbf P 4 := W4 acc P 4 = 50.3 lbf P 5 := W5 ace P 5 = 100.5 Ibf 18" ,
6 6 W := (W j + W2+W 3+W4 + W S)*1*9 P h w . 421.3 ibf h)M P := P 1+P 2+P 3+P 4+P S
" P = 273.9 lbf f M := P g-((120.- 18) in) + 2P -((126 - 18) in) +3P -((138 - 18) in) +4P -((150 18) in) .
+ P5-((162 - 18) in)
M = 348712 lbfin 18 4 pullout _A = 2632.5 Ibf pullout _A := W + + ,
18,n s 18in P.18 in ullout_8 = 2211.1 Ibf pullout _B := +
18 ,in 18in shear _A 2:= E shear _A = 136.9 lbf ,
shcar_B := shear _B = 136.9 lbf Page 12 CBLETRAY.MCD
~
+. _
- .. _ ._ . _ - . . - . _ = .
Vermont SQUG GlPYcnkee USI-A46: Sample Evaluations for C:ble P geTray (3 Deadweight 3upp i Limited Analytical Reviews ed l-s - ,
P-answ +4
-CheckWeld at C: Area of weld for a P1000 = AweM_P1000 := 31.625 in 2 2 pullout _B + shear _B 54.4 IDI gres , f*= in A weld _P1000 Allowable load = F w seismic = 3213.0 $ } Weld OK
_ in
- Check Bolts at C 2 2
.C compression := pullout _B + shear _B C compression = 2215.4 lbf Sup capacity = 2 F slip _alc.ag = 3000.0 Ib and pullout capacity = 2 F pullout = 4000.0 lb
- Bolts are adequate.
- Check connection at A-
-. - Check Weld at A:
~ ~
f res = 405.5 +h f res: Awegd m
. Allowable load = Fw seismicin= 3213.0 $ } Weld OK
- Check Bolts at A-pullout _A = 2632.5 lbf < Pullout capacity = 2 F pullout = 4000.0 lb } Bolts OK shear _A = 136.9 Ibf < slip along capacity = 2 F slip _along = 3000.0 lb } Bolts OK
- Check Embedded Strut pullout _A = 2632.5 lbf< pullout capacity = F embed. pullout _ft seismic = 4000.0 $ } Embed
- Connection at B is OK by comparison to connection at A.
Support members and connections are OK for Lateral Load Check l - The support is not a fixed-end rod hanger.
I CONCLUSION: The support is seismically adequate per the analytical review guidelines of Section 8 of the GIP.
Page 13
! c8LETRAY.MCD 4
Vermont Ycnkee UZI-A46: Sample Evaluations for Cable Tray Deadweig Pcge h}hSupports of '2F SQUG CIP Limited Analytical Reviews L.
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Vermont Yc nkee USI-A46: Sample Evaluations for Cable Tray Deadweight Supports SQU3 CIP Limited Analytical Reviews P;g3 15 of'l6 )
) w -
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I l
- REVIEW NUMBER 8: RB 252 SW 1
- CHECK DEAD LOAD:
span := 6.33 ft l 24"
-- m rn 1 . . .
. s g8s =
to :
! ; e 33" W1 !
W2 W4 :
W3
~
Jot _5 :
W6 _
W9 W7 W 10 W8 _ _ W 11 1
=id-ii29 W j := spant_24_25 W j = 59.3 lb W2 := span wt_24_50 W2 = 118.71b W 3 := W2 W4 := W2
.W 5 := spant_24_100 W 5 = 237.4 lb W 6 := W5 W7 := W2 W 8 := 8.33 ft-(wt_24_100) W 8 = 312.4 Ib W g := (span wt_24_50) + (3 ft wt_24_100) W g = 2312 Ib W jo := W2 W qq := 2-(span).(M_24_50) W qq = 237.4 lb COLITRAY.MCD Page 22
+4
Vermont Ycnkae U21446: Sample Evaluation 3 for Cable Tray Deadweight Supports SQUG CIP Limited Analytical Reviews Page Ib of if i
i ~ r f
ILEM ew
- Horizontal P1001 struts supporting the trays are enveloped by Reviews 1 - 7. Review #1 has a load of 375 lb.
- CHECK ANCHORAGE The support is secured to the ceiling by (2) Unistrut spring nuts in an embedded strut. ,
Total dead weight = Wt := W g + W 2-W 4 3+W4+W S+W6+W 7+W 8+Wg.
+W 10 + W 11 l
- Check Weld, Strut to Plate ;
f I res = 294'"h < Fw normat = 1890.0 res ; A weld I" $ } Weld OK
-Check Spring Nuts
- } Sprina nuts OK pullout := pullout = 954.2 A < F pullout = 2000.0 lb 2 bolt bolt l
-Check Embedded Strut pullout;= Wt pullout = 1908.5- < F embed. pullout = 2000.0 D } Embed strut OK l
Support members and connections are adeauste for 1 x Dead Load l 1
- CHECKVERTICAL CAPACITY: Per Figure 8-6 of the GIP the next check is a 3 x Dead Load check of the primary connections and the anchorage. This will be done by multiplying the previous checks by a factorof 3.
-Check Spring Nuts pullout := . t 2 bolt pullout = 2862.7 - > F pullout = 2000.0 Ib } Sprino nuts are not Adequate CBLETRAY.MCO Page 23 l
l
Vermont Ycnkee USI-A46: Sample Ev:luations for Cable Tray Deadweight Supports SQUG CIP Limited Analytical Reviews Pcge (~7 of 1!.5"__
J r ,
i26\/le7 Me>
-Check Embedded Strut '
pullout := 3 Wt pullout = 5725.4 A > F embed _ pullout _ seismic = 4000.08 Embed
} strut not Adeauste bolt ft Support members and connections are not adequate for 3 x Dead Load
- Because of the brace the support may not respond in a ductile manner. Therefore it must be l
subjected to a lateralload check in accordance with Secticn 8.3.4 of the GlP.
- The lateral load check consists of subjecting the support to a loading of 1 x dead load plus a transverse acceleration = 2.5 x floor ZPA where the raceway system is attached.
For Elevation 280' of the Reactor Building find the floor OBE E-W = ZPAOBE := 0.10 g . j 1
ZPA SSE := 2 ZPAOBE ZPASSE = 020 g l
ace := 2.5 ZPASSE acc = 0.50 g I
P q := W4 acc P q = 29.7 lbf P 2 := W2 acc P 2 = 59.3 lbf l
P 3 := W 3. ace P 3 = 59.3 ibf P 4 := W4 acc P 4 = 59.3 lbf 1
P 5 := W5 ace P 5 = 118.7 lbf P 6 := W6 acc P 6 = 118.7 lbf P 7 := W7 acc P 7 = 59.3 lbf P 8 := W8 acc P 8 = 1562 lbf P g := W g ace P g = 115.6 lbf P 10 := W 10. ace P 10 = 59.3 lbf P 99 := W gg acc I gg = 118.7 lbf P := P q + P 2+P 3+P 4+P S+P 6+P 7+P 8 + P g + P jo + P jj P = 954.2 lbf CBLETRAY.MCo Page 24
.4
Vermont Ycnkee USI-A46: Sample Evaluations for Cable Tray Deadweight Supports ,
SQUG CIP Limited Analytical Reviews Page la of 1F
> + _
Eaview 448 )
M := P g-(57 in - 18 in) + P 2 (66 in - 18 in) + P3-(75 in - 18 in) + P4-(117 in - 18 in)
+ P 5-(129 in - 18 in) + P 6-(141 in - 18 in) + P7-(153 in - 18 in) + P 8-(165 in - 18 in) {
+ P g-(141 in - 18 in) + P 10-(153 in - 18 in) + P q1-(165 in - 18 in)
- M = 111683.7 Ibfin
- Check Anchorage P 18 in + M g ,$,g ;
pullout := pullout = 3638.8 5 2 bolt bolt <
l Spring Nuts and embed are not adequate for the lateral load. l I
CONCLUSION: The support is n2t seismically adequate per the guidelines of the GIP.
i l
COLETRAYMCD Page 25
l Vermont Ycnkee USI A46: Sample Ev luations for Cable Tray Deadweight Supports of 15 SQUG GIP Limited Analytical Reviews Page 19 4! Rcweu
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, Vermont Yankee USI-A46: Sample Eyc.luations for Ccble Tray Deadweight Cupports SQUG CIP Limited Analytical Reviews P ge 2.0 of SS
- REVIEW NUMBER 9: SWGR ROOM
- CHECK DEAD LOAD:
13-1/2"[
[ 2-1/2" Y Y hbbh 10" Wie o W2
- W3
- W4 " -
W j := 5.75 A-((4 C 4_ inch) + C 3_ inch) W q = 453.1 lb W2 := 4.5. A-(2)-(C 1 .5_ inch) W2 = 32.4 lb W3 := 7.5 A.(wt_18_100) W 3 = 210.9 lb W4 := 6.75 A.(wt_12_100) + (2.5 A)-(31 .C5_ inch + 2 C 2_ inch) . W4 = 201.9 lb
+ 6.A 3.8- (p100j)
COLETRAY.MCO Page 26
-. . - = - . .. _ -- - - . - _ _ . -. _ . .
Vermont Ycnkee USI-A46: Sample Evaluations for Cable Tray Deadweig Supports SQUG CIP Limited Analytical Reviews Page 1 of25
~'
1 C /
S CW \\ %= Y
- Check licit 06tal P1001 Supporting W 1:
1 P1 P2 P2 P2 P2 ,
)
U U 1r U U P j := 5.75 ft (C 3_ inch) P q = 73.6 Ib 6" p 2 := 5.75 ft.(C 4_ inch) P 2 = 94.9 lb 11" 16" M := Pg 30 in + P 2-(21 + 16 + 11 + 6) in 21" M = 7331.3 Ib in 30" i 1
o := E o = 12.8 ksi < F b = 25.0 ksi } MemberOK Sx l
- Check Welding of Strut to Plate:
IPj+4P 2 I f M 32 fres;* I res = 2083 I" lb I + .
3( Aweld j (S weldj fres = 2083- > F w normal = 1890.0-I res 10% overstress judged adequate due to
= 1.10 conservatism in assuming all conduits to ;
p W nonnal i
I -
be full. l r !
, l 3
I i
+
E i CBLETRAY.MCD Page 27
Vermont Ycnkee USI-A46: Sample Evaluations for Cable Tray Deadweight Cupposis SQUG CIP Limited Analytical Reviews Pcge 1S of 'l5
k@l t=. W M -
- CHECK ANCHORAGE The support is secured to the ceiling by (2) 1/2" Phillips Red Head anchor bolts.
- Check P1000 Strut S P1000 := 0.203.d P P := W g i W 2+W 3+W 4 V v P = 898.3 Ib v
a := 2.5 in b := 13.5.in 13-1/2" 2-1/2 g ., P.a.b M - 1894.9 ib.in a+b M
o = 9.3 ksi < F b = 25.0 ksi } MemberOK o :=
I S P1000
- Check Anchor Bolts: From Review # 2 find a 1/2" Phillips Red Head anchor bolt has an allowable pulloutload = F t= 1717.5 lb .
pullout := P l 3.5} pullout = 757.9 A < F 1 = 1717.5 Ib } Anchor Bolts OK
( 16 / bolt Support members and connections are adeauste for 1 x Dead Load j l
l Page 28 CBLETRAY.MCD
. -- = . - __- - - -
l- '
Vermont Yankee U :-A46: Sample Evaluations for Cable Tray Deadweight Supports SQUG CIP Limited Analytical Reviews P;;ge 13 of16 l
l
> % /
M.@/IEWM l
l 1
l
- CHECK VERTICAL CAPACITY: Per Figure 8-6 of the GlP the next check is a 3 x Dead !
Load check of the primary connections and the anchorage. This will be done by multiplying the previous checks by a factor of 3.
- Check Welding of Strut to Plate:
l M := P g 30 in + P2-(21 + 16 + 11 + 6) in M = 7331.3 Ib in
, \
(Pq+4PI 2 /M 1 2 fres := 3- +l l f res = 6250 lb !
3i A weld / S
( weld) in I f res = 6250 h > F w seismic = 3213.0} Weld $ is Not Adeauste !
in -
in
- CHECK ANCHORAGE I _, - Check Weld of Vertical P1001 to P1000: l I
f P \
f res = 415 Ib f res := 3 i I" (A weldj i
f res = 415 h < F w seismic = 3213.0 $
} Weldis OK in in l
l -Check Anchor Bolts !
l 13.5 puliout = 2273.8 A > F =t 1717.5 lb pullout := 3-P j } Anchor Bolts are not
( 16 j bolt i Adeauste l
Support members and connections are not adeauate for 3 x Dead Load l
j CBLETRAY.fACD Page 29 l
! l l.
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. Vermont Ycnkee U21 A46: Sample Evnluations for Cable Tray Deadweight Supports 7A of f5i SQUG ClP Limited Analytical Reviews Pcge 1 IN N
- Because of the brace the suppod may not respond in a ductile manner. Therefore it must be subjected to a lateralload check in accordance with Section 8.3.4 of the GlP.
- The lateral load check consists of subjecting the support to a loading of 1 x dead load plus a transverse acceleration = 2.5 x floor ZPAwhere the raceway system is attached.
l For Elevation 262.5' of the Control Building find the floor SSE E-W = ZPA := 0.34 g .
acc := 2.5 ZPA acc = 0.85 g ,
1 P $ := W j.acc P g = 385.1 lbf 12' f
P 2 = 27.5 -Ibf j P 2 := W 2 acc i P 3 := W3.acc P 3 = 179.3 lbf l
P 4 := W4 acc P 4 = 171.6 lbf 6 c P e
P = 763.6 lbf y( P := P $+P 2+P 3+P 4 W := (W $+W2+W 3+W4 )1 g W = 898.3 lbf q
M := P g 18 in + P 2 30 in + P3.38 in + P447 in M = 22636.3 lbfin P 10 in pullout _A = 3421.0 lbf pullout _A := W + +
12 in 12 in M P.104 pullout _B = 2522.7 lbf pullout B :=
+
12 in 12 in shear _A := shear _A = 381.8 lbf~
shear _B := shear _B = 381.8 lbf Page 30 CBLETRAY.MCo A
w
~,
Vermont Ycnkee USI A48: Sample Evaksations for Cable Tray Deadweight Supports '
SQUG ClP Limited Analytical Reviews Page '2.5" ofg n % / 'h DIN .% ;
-Check Weld at 8 and C: Area of weld for a P1000 = AweW P1000 := 31.625 in -
tres ::
W- +h8 2 f'** 523.4 A in weld _P1000 Allowable load = F, m = 3213.0 $ } Weld OK in
- Check Weld at A-pullout _A + har_A2 .
f , := I res = 529.6 b
- Ag h Allowable load = F, g = 3213.0 $ } Weld OK in 1 l - Check Anchor Bolts
- From Review # 2 find a 1/2" Phillips Red Head anchor bolt has an allowable pulloutload = Ft = 1717.5+lb _
w pullout := pullout _A pullout = 3421.0 *M > F t= 1717.5 lb } Anchor Bolts Not L Adeouste Support members and connechons are Not Adeouate for Lateral Load Check l
l l
CONCLUSION: The supportis not seismicaisy adequatep.c Ae.gp ,Aws, l
Of #$e 6M l
4 i l 5
i i
1 C8LETRAY.WCo Page 31 i
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