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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
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. ViLRMONT YANKEE NUCLEAR POWER CORPORATION Ferry Road, Brattleboro, VT 05301-7002 y ,,, I ENGINEERING OFFICE f
. 580 MAIN STREET
. BOLTON, MA 01740 (508)779-6711 November 15,1996 BVY 96-145 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
References:
(a) License No. DPR-28 (Docket No. 50-271) )
(b) Letter, WNPC to USNRC, BW 96-58, dated May 28,1996 l (c) Letter, USNRC to WNPC, NW 96-117, dated June 28,1996 (d) Letter, WNPC to USNRC, BW 96-94, dated July 26,1996 (e) Telecon, USNRC to WNPC, November 8,1996 (f) Underwriter's Laboratory Test Report, File R10925-1, dated April 10,1984
Subject:
Response to Request for Additional Information Regarding Vermont Yankee Request for Exemption from 10 CFR Part 50, Appendix R j in Reference (b), Vermont Yankee requested exemption from the requirements of 10CFR50, Appendix R, Section Ill.G, " Fire protection of safe shutdown capability," to permit use of Rockbestos Firezone*R fireproof cable in plant areas th::t 9 quire enclosing cables in a fire barrier having a 1-hour fire rating. The plant areas identi' J in the exemption request were the Cable Vault and the 280 foot elevation of the Reactor B/ Jing.
In Reference (c), the NRC requested additionalinform aon needed to complete review of our exemption request. In Reference (d) Vermont Yankee submitted the requested information and revised the exemption request so that it now applies to the use of Rockbestos Firezone*R cable only in the Cable Vault.
In Reference (e), the NRC requested further information regarding our request. The information requested is attached.
We trust that the information provided is acceptable; however, should you have any questions, please contact this office.
Sincerely, VERMONT YANKEE NUCLEAR POWER CORPORATION 1
[ffftpf 2000$
James J. Duffy Licensing Engineer
[ ./
9611200213 961115 PDR ADOCK 05000271 F PDR
4 VERMONT YANKEE NUCLEAR POWER CORPORATION United States Nuclear Regulatory Commission
'Noverbber 15 1996 '
. Pags 2 of 2 Attachment 1: Response to Request for Additional Information Attachment 2: Rockbestos Firezone*R cable Vendor information c: USNRC Region I Administrator USNRC Resident inspector - VYNPS USNRC Project Manager- VYNPS
o VERMONT YANKEE NUCLEAR POWER CORPORATION United States Nuclear Regulatory Commission
- Noveinber 15,1996 Attachment 1
- Page 1 of 3 ,
l Request for Additional Information Vermont Yankee Nuclear Power Station Request for Additional Information #1 Describe and justify the differences between the tested (Reference (f)] and installed Firezone*R cable configurations. Describe why and how the tested configurations bound the installed 4
configurations. In addition, state the maximum temperature attained during the test and provide the limiting temperature for cable damage.
Response to Request for Additional !nformation #1 The cable which is the subject of Vermont Yankee's exemption request, installed in the Cable l Vault, is a two-conductor (2/C) #14 AWG Firezone*R cable with a stairless steel sheath (see Attachment 2). The cables tested in Reference (f) included a 3/C #14 AWG cable. As demonstrated below, the 2/C cable is identical to the 3/C cable in all critical fire protection attributes except for having one less conductor. Also, as demonstrated below, the test .
I configurations exposed the Firezone*R cable to conditions more severe than the instal;ed configuration. Based on these facts, the tested configurations bound the installed configuration and therefore the use of the 2/C Firezone*R cable requested in Reference (b) is considered acceptable.
Cable Construction As described in Attachment 2, all Firezone*R cables have the same cable jacket construction including: flame retardant binder tape, glass braid covering and a continuously welded, corrugated stainless steel sheath. Additionally, each individual conductor in a #14 AWG Firezone*R cable has the same conductor construction including: conductor size, composite inorganic layer fire barrier, silicone rubber insulation, mica tape and glass braid conductor i
covering with high temperature finish. Finally, conductor to conductor spacing and conductor to cable jacket spacing are the same for the installed 2/C cable as for the tested 3/C cable. The critical electrical insulation properties of the cable when exposed to the fire are therefore the
! same.
Fire Test Confiauration The configuration of the 2/C cable installed at Vermont Yankee is less severe than the test configuration of the 3/C cable in Reference (f). The installed 2/C cable is routed outside of
- cable trays, away from non-fire-resistant electrical cables (see description of 2/C cable routing provided in Reference (d)]. As described in Reference (f), the tested 3/C cable was placed in a cable tray assembly among non-fire-resistant electrical cables to simulate the fuel loading of an actual installation. Despite the additional exposure of ignited non-fire-resistant cables, a configuration more severe than Vermont Yankee's configuration, the Firezone*R cable remained functional throughout the test.
Also, the installed 2/C cable is used in a 120Vac circuit and the cable insulation is rated for 600Vac. The tested cable was subjected to a 78 minute fire exposure with the furnace temperatures controlled in accordance with the Standard for Fire Tests of Building Construction
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r VERMONT YANKEE NUCLEAR POWER CORI' ORATION United States Nuclear Regulatory Commission l
' Noveinber 15,1996 Attachment 1
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Page 2 of 3 and Materials, ASTM E119. During the fire endurance test, the 3/C cable was connected to three phase Y voltages of 480/277V and 960/555 Vac (Reference (f), p. 32]. This test configuration is clearly more severe than the installed configuration. The temperatures measured on the stainless steel sheath of the tested cable are contained in Appendix D of Reference (f). The maximum ambient temperature attained was 1740'F and the maximum 3/C cable temperature attained was 1671.9'F. Although the limiting temperature for cable damage was not determined during the test, the test results demonstrate that the limiting temperature
, for cable damage is in excess of that required to achieve a one-hour fire rating.
1 Therefore, because the 2/C Firezone*R cable installed at Vermont Yankee is essentially the same in construction and fire protection features as the tested 3/C Firezone*R cable and because the 3/C cable passed an ASTM E119 fire test whose configuration and test conditions were more severe than the 2/C cable installation at Vermont Yankee, use of the 2/C
! Firezone*R cable is bounded by the tested configuration and its use as a 1-hour fire barrier is i therefore acceptable.
Reauest for AdditionalInformation #2 Describe the conditions and functionality of the Firezone*R cables throughout the test. Indicate whether the cables were energized and carrying load or de-energized, as well as whether the
- cables were capable of performing their function. Discuss the criteria used to determine functionality of the cable such as insulation resistance, physical damage, or others.
Response to Reauest for Additional Information #2
, "The fire endurance test was conducted with the furnace temperatures controlled in accordance with the Standard for Fire Tests of Building Construction and Materials, ASTM E119."
- Reference (f), p.15 4
"Immediately before the fire endurance test, the fire resistant cables were energized with predetermined steady-state ac electrical currents. The cables remained energized throughout the fire exposure except for a 10 s period immediately preceding an inrush current test on each fire resistant cable. Following the fire endurance test, the cables were deenergized for the water hose stream test. Following the water hose stream test, the cables were again energized with predetermined steady state ac electrical currents. The cables remained energized throughout a 93 h cooldown period except for a 10 s period just prior to the application of four supplemental inrush current tests. Following the 93 h extended cooldown period the cables were again deenergized for a second hose stream test. Immediately following the second hose stream test the cables were subject to a final inrush current test."
- Reference (i), p.1 "In addition to the low voltage ac electrical current applied to each conductor of the nine fire resistant cable configurations, each fire resistant cable was energized with a de voltage and monitored continuously for electrical faults. The electrical fault monitor panel was connected to
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VERMONT YANKEE NUCLEAR POWER CORPORATION l
- ~. United States Nuclear Regulatory Commission Nove'mber 15,1990 Attachment 1 Page 3 of 3 an automatic data logger which scanned each circuit and provided a printed record to show electrical faults."
- Reference (f), p.17 The test results indicated that no " electrical faults occurred in any of the nine fire resistant cable configurations." To " substantiate the determination that no electrical faults were present in the nine fire resistant cable configurations, insulation resistance and dielectric voltage-withstand tests were conducted on each conductor of the nine cables. The results of the insulation resistance and dielectric voltage-withstand tests are contained in Appendices B and C, respectively," of Reference (f).
- Reference (f), p. 23 "As evidenced from the tables in Appendices A, B and C, (electrical current, insulation resistance and dielectric voltage-withstand measurements) each of the nine fire resistant cable configurations in the full-scale test assembly remained electrically functional during the fire endurance test and during the extended cool-down period."
- Reference (f), pp. 31-32 Request for Additional Information #3 Descr be the magnitude of current loading during the testing in Reference (f).
l Response to Reauest for AdditionalInformation #3 The following table provides a comparison of loads carried by the tested and installed cables:
Cable Type Steady State Current inrush Current Tested: 3/C #14 AWG ~4A* ~ 17 A (for 30 sec)*
Installed: 2/C #14 AWG 0.2 A 1.3 A (for 8.3 msec)
- See Appendix A, p. A3, of Reference (f) for exact values for each conductor l
The latest vendor catalog establishes conduction ampacity at 1700 F (based on an 1800 F conductor temperature) as follows:
Cable Type Ampacity at 1700 F ambient 3/C #14 AWG 14.9 A 2/C #14 AWG 14.9 A The significantly higher current loading of the tested cable and the manufacturer's published l ampacity provide further evidence that the use of the 2/C Firezone*R cable at Vermont Yankee is bounded by the tested configuration and is therefore acceptable.
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. Firezone'" R '
Appenda. .. R ..
i t Armor (optional *) Binder Ta'pe C$nductor
! . Continuously welded : Flame retardant lL stranded ;
Flexibly Fireproof Cable l corrugated , l nickel-coated
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Class 1E Nuclear l l Overall Covering . Fire Barrier 1 i Glass brald ~ , i ~ Mica Tape Composne Inorganic layer Spec. RSS-5-144 Conductor Cov'ering , LOCA Dielectric l i
-Glass braid - -i Stitcone rubber '
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! Scope l Firezone*Ris a fireproof cable specifically designed to address redundant safety l circuit requirements within nuclear generating stations. This unique Class 1E nuclear qualified cable system insures safety-related circuit integrity in the event of a fire as required by Appendix "R". (Code of Federal Regulations: Title 10, Part
- 50.48). It is intended for use on low voltage control, power and instrumentation l circuits and can be supplied in either armored or unarmored
! Features Performance Standards Conductor:
l Flexible strand, high temperature, nickel-
- Cost-efficient altemative to thermal wrap-
- Minimum one hour fire rating at 1700*F c ted copper conductor ping of cable trays or cable re-routing as defined by the ASTM standard E-119 Fire Barrier:
- Can be installed within trays containing
- Greater than three hour fire survival at Composite inorganic layer i typical plant cables 1500*F LOCA Dielectric:
l
- Other cables within tray do not have to be
- Class 1E qualified in accordance with Silic ne rubber insulation layer l derated (as is necessary with ampacities IEEE-383 and IEEE-323. (Rockbestos l for cables inside thermally wrapped trays) Report QR-9801) Conductor Covering:
I
- Additional circuits can be easily added
- Full ASTM E-119 fire test report avail- Mica tape and glass braid with high tempera-
- Does not require costly inspection, main- able under UL report file #R109254, ture finish l
tenance and record keeping associated pro)ect #84NK2320 (Note: this is not a Circuit identification:
with tray wrapping UL listed cable) White braids with colored tracers
- Full traceability provided
hr vertical tray flame test cabling:
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- Silicone rubber insulation layer is in ac_ Required number of conductors cabled I
- Nuclear qualified with a minimum 40- cordance with ICEA standard S-19-81 Binder Tape:
, year thermallife expectancy at 90*C**
- Quality Assurance program in accordance Flame retardant binder tape j with 10 CFR Appendix B Armor: (optional *)
f Continuously welded, corrugated, stainless i steel sheath 1
- Unarmored cable must be installed in steel conduit l **Sihcone rubber insulation has an inheren' 125'C 40-
- year thermal hie.
l 'The Rockbestos Company 285 Nicoll Street New Itaven, Connecticut 06511 (203)772-2250 800 327-7625 US-7 I
i
! Firezone*R l Appendir "R" i Fireproof Cable l 90*C, 600 Volt Class 1E Nuclear l .
i ,
(Inorganic Layers) spec. nss-5444 1
4 .
I Stainless Steel Armored Single Conductor Nominal Overall Approximate Product Number of Conductor Number of Diameter Diameter Net Weight Code Conductors Size Strands (In) (In) (Ibs/M')
F54-3017 2 14 AWG 19 .27 .78 260 i F54-3041 3 14 AWG 19 .27 .92 320 i F54 3045 4 14 AWG 19 .27 .96 390 j F54-3053 7 14 AWG 19 .27 1.00 540 t
! F54-3004 2 12 AWG 19 .29 .84 290 l F54 3042 3 12 AWG 19 .29 .96 370 F54 3046 4 12 AWG 19 .29 1.00 450 F54 3054 7 12 AWG 19 .29 1.13 650 F54 3040 2 10 AWG 49 .33 .96 360 F54-3005 3 10 AWG 49 .33 1.00 430 F54-3047 4 10 AWG 49 .33 1.00 530 F54-3055 7 10 AWG 49 .33 1.33 820 3
l F54 3043 3 3AWG 133 .39 1.26 600 l F54 3048 4 8AWG 133 .39 1.26 740 l F54-3044 3 6AWG 133 .44 1.26 730 t
' F54-3049 4 6AWG 133 .44 1.46 930 F54-3014 3 4AWG 133 .54 1.50 1150 F54-3050 4 4AWG 133 .54 1.56 1220 F54 3016 3 2AWG 665 60 1.61 1470 F54-3051 4 2AWG 665 .60 1.71 1650 F54-3057 3 1AWG 817 .67 1.80 1630 F54-3052 4 1AWG S17 .67 2.02 2100 Unarmored (Must be installed in conduit)
Fb4 3019 2 14 AWG 19 .27 .62 150 F54-3025 3 14 AWG 19 .27 .66 200 l F54-3030 4 14 AWG 19 .27 .73 250 F54-3021 7 14 AWG 19 .27 .88 400 l
F54 3010 2 12 AWG 19 .29 .66 170 F54 3020 3 12 AWG 19 .29 .70 240 F54-3031 4 12 AWG 19 .29 .78 300 F54 -3009 7 12 AWG 19 .29 .94 480 l
F54 3024 2 10 AWG 49 .33 .73 220 F54-3011 3 10 AWG 49 .33 .78 290 F54 3032 4 10 AWG 49 .33 .87 380 f 54 3038 7 10 AWG 49 .33 1.05 620 F54 3026 3 8AWG 133 .39 .93 430 F54 3033 4 8AWG 133 .39 1.03 560 F54 3027 3 6AWG 133 .44 1.02 550 F54-3034 4 6AWG 133 .44 1.14 720 F54-3028 3 4AWG 133 54 1.15 760 F54-3055 4 4AWG 133 .54 1 29 990 F54-3029 3 2AWG 665 60 1 29 1070 F54 -3036 4 2AWG 065 60 1 44 1100 F54 3058 3 1AWG Hl7 67 1 51 1180 f 54 3037 4 1AWG H17 67 1 68 1800
[1% 8 rn io "The Hot kbestos Company 2H5 Nicoil Street New flaven, Cmme< tic ut 06511 (203)772 2250 800 327 7625