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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] Category:UTILITY TO NRC
MONTHYEARML20059J2831990-09-10010 September 1990 Forwards Updated Operator Licensing Exam Schedule for FY91, FY92,FY93 & FY94,per Generic Ltrs 90-07 & 89-12 ML20059D9831990-08-28028 August 1990 Forwards fitness-for-duty Program Performance Data for 900103-0630,per 10CFR26.71.NRC Review of Data Will Provide Realization That Positive Testing Rate Extremely Low & Limited to pre-access Testing Population BVY-90-087, Forwards Addl Info on Use of RELAP5YA Program for LOCA Analyses.Proprietary Encl Withheld1990-08-28028 August 1990 Forwards Addl Info on Use of RELAP5YA Program for LOCA Analyses.Proprietary Encl Withheld BVY-90-086, Responds to NRC Re Violations Noted in Insp Rept 50-271/90-06.Corrective Actions:Incident Rept Initiated & All Required Locking Devices in Place by 9007061990-08-24024 August 1990 Responds to NRC Re Violations Noted in Insp Rept 50-271/90-06.Corrective Actions:Incident Rept Initiated & All Required Locking Devices in Place by 900706 ML20059F6681990-08-22022 August 1990 Comments on Review of Amend 115 to License DPR-28,including Safety Evaluation.Requests Explanation of Statement in NRC Re How NRC Considers Comments & What Resolution Could Be for Each Util Comment in BVY-90-085, Informs That Sys Testing & Operator Training Successfully Completed & SPDS Declared Operable on 900813.Util Intends to Operate SPDS in Parallel W/Original Honeywell Gepac Plant Computer Until mid-Nov 19901990-08-15015 August 1990 Informs That Sys Testing & Operator Training Successfully Completed & SPDS Declared Operable on 900813.Util Intends to Operate SPDS in Parallel W/Original Honeywell Gepac Plant Computer Until mid-Nov 1990 BVY-90-084, Notifies NRC of Intentions to Install Test Fuel Assemblies & Test Control Blades During Cycle 15 Refueling Outage in Sept 19901990-07-24024 July 1990 Notifies NRC of Intentions to Install Test Fuel Assemblies & Test Control Blades During Cycle 15 Refueling Outage in Sept 1990 BVY-90-082, Informs That Effective 900723 Facility Implemented Rev 4 of Procedure Generating Package & Corresponding Revs to Eops. Revs Developed Per Rev 4 of BWR Owners Group Emergency Procedure Guidelines1990-07-24024 July 1990 Informs That Effective 900723 Facility Implemented Rev 4 of Procedure Generating Package & Corresponding Revs to Eops. Revs Developed Per Rev 4 of BWR Owners Group Emergency Procedure Guidelines BVY-90-071, Forwards Rev 2 to Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21)1990-07-20020 July 1990 Forwards Rev 2 to Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21) BVY-90-078, Forwards List of Refs for Proposed Change 161 to Facility OL & Tech Specs1990-07-17017 July 1990 Forwards List of Refs for Proposed Change 161 to Facility OL & Tech Specs BVY-90-072, Forwards Supplemental Effluent & Waste Disposal Semiannual Rept for Third & Fourth Quarters 1989,Including Annual Radiological Impact on Man for 19891990-06-27027 June 1990 Forwards Supplemental Effluent & Waste Disposal Semiannual Rept for Third & Fourth Quarters 1989,Including Annual Radiological Impact on Man for 1989 ML20043G4351990-06-15015 June 1990 Requests Temporary Waiver of Compliance from Tech Spec Requirements for Limiting Conditions for Operation for Certain post-accident Monitoring Instrumentation Listed in Tech Spec Table 3.2.6.Parameters Listed ML20043E4011990-06-0808 June 1990 Responds to Second Request for Addl Info on Use of RELAP5YA. Explanation Re Why More Accurate View Factor Calculation Not Included in Huxy Code Addressed ML20043C6131990-06-0101 June 1990 Forwards YAEC-1659-A, Simulate-3 Validation & Verification. ML20043C5991990-06-0101 June 1990 Forwards Accepted Version of YAEC-1683-A, MICBURN-3/ CASMO-3/TABLES-3/SIMULATE-3 Benchmarking of Vermont Yankee Cycles 9 Through 13. ML20043C4821990-05-30030 May 1990 Informs of Three Organizational Changes That Will Become Effective on 900601.WP Murphy,Jp Pelletier & DA Reid Will Be Senior Vice President of Operations,Newly Created Vice President of Engineering & Plant Manager,Respectively ML20043B7561990-05-23023 May 1990 Informs That Util Intends to Utilize Relationship Between Frosstey & FROSSTEY-2 to Support Cycle 15 Calculations.Nrc Approval of FROSSTEY-2 Needed by Aug 1990 for LOCA Analysis Program ML20043B6481990-05-17017 May 1990 Forwards Rev 19 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) BVY-90-058, Forwards Public Version of Vermont Yankee Nuclear Power Station Emergency Response Preparedness Exercise 1990. Exercise Scenario Package Includes All Info Pertinent to Performance of Exercise Scheduled for 9007181990-05-17017 May 1990 Forwards Public Version of Vermont Yankee Nuclear Power Station Emergency Response Preparedness Exercise 1990. Exercise Scenario Package Includes All Info Pertinent to Performance of Exercise Scheduled for 900718 ML20042G9061990-05-10010 May 1990 Forwards Proprietary Supplemental Info to 900419 Response to NRC 900309 Ltr Re FROSSTEY-2 Fuel Performance Code.Info Withheld ML20042F6471990-05-0404 May 1990 Ack That NRC Will Issue Supplementary Info to NRC 900307 Request for Installation of Neutron Flux Monitoring Instrumentation That Conforms to Requirements of Reg Guide 1.97 & 10CFR50.49 at Plant ML20042E7291990-04-23023 April 1990 Forwards Pages Omitted from 900314 Revs 16-18 to Physical Security Plan.Revs Withheld ML20012F3511990-03-30030 March 1990 Provides Supplemental Response to Station Blackout Rule (10CFR50.63).Util Will Use Alternate Ac Power Source Available within 10 Minutes of Onset of Station Blackout to Meet Requirements of Station Blackout Rule ML20012D0301990-03-19019 March 1990 Forwards Response to Generic Ltr 89-19 Re Resolution of USI A-47.Feedwater Sys Trip Relays,Interfacing W/Feedwater Pump Control Circuitry,Powered from Supplies Originating from safety-related Dc Sources ML20012D0241990-03-16016 March 1990 Forwards Supplemental Info Re Feedwater Check Valve V28B Flaws Evaluation,Per NRC Request.Util Remains Committed to Replacement of Subj Valve During Upcoming 1990 Refueling Outage ML20012C6381990-03-15015 March 1990 Forwards Vermont Yankee Nuclear Power Corp Financial Statements 891231,1988 & 1987. ML20012C6071990-03-15015 March 1990 Forwards Method for Generation of One-Dimensional Kinetics Data for RETRAN-02, Per NUREG-0393 & 891211 Request ML20012B8311990-03-0909 March 1990 Forwards Proprietary Vermont Yankee Evaluation Model Sample Problem 0.7 Ft(2) Break in Recirculation Discharge Loop, in Response to 900208 Telcon.Rept Withheld (Ref 10CFR2.790) ML20012B6131990-03-0909 March 1990 Informs of Schedular Changes Made W/Regard to Plant Licensed Operator Requalification Training Program ML20006E8871990-02-15015 February 1990 Provides NRC W/Results of Licensee Review of Design Bases & Operability Status of torus-to-reactor Bldg Vacuum Breakers ML20011E6791990-02-0505 February 1990 Responds to Weaknesses Noted in SALP Rept 50-271/88-99 for Jul 1988 to Sept 1989.Implementation of Emergency Response Facility Info Sys Nearing Completion & Remaining Safety Class Vendor Manuals Will Be Completed During 1990 ML20006D1571990-02-0202 February 1990 Responds to 891226 Request for Addl Info Re YAEC-1683 on MICBURN-3/CASMO-3/TABLES-3/SIMULATE-3 Benchmarking.Hot Eigenvalue Std Deviation on Table 5.7 of YAEC-1683 Reduced to 0.00098 w/SIMULATE-3 ML20006B1351990-01-22022 January 1990 Forwards Responses to Generic Ltr 89-13 Re Svc Water Sys Problems Affecting safety-related Equipment.Establishment of Program Revs Prior to Startup from Next Refueling Outage, Scheduled for Fall 1990,planned ML20006A4441990-01-16016 January 1990 Forwards Revised Page 127 of Tech Specs to Clarify Proposed Change 134, Rev of Pressure Suppression - Reactor Bldg Vacuum Breaker Sys Operability Requirements. Change Involves Adoption of Language Consistent W/Bwr STS ML19354E8001990-01-16016 January 1990 Forwards Addl Info Re Testing of Cable Vault C02 Suppression Sys During 891031-1102,per NRC 890518 & 0821 Requests.Encl Final Test Rept Demonstrates That Carbon Dioxide Sys Will Satisfy Design Bases for Greater than 10 Minutes in Room ML20005G0841990-01-10010 January 1990 Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking of high-hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or Valves of Similar Design ML20005E8201990-01-0202 January 1990 Forwards Minutes of NRC 890907 Meeting W/Util in Rockville,Md Re Util LOCA Analysis Program.List of Attendees Also Encl ML20005F0551990-01-0202 January 1990 Informs That Util Has Implemented Fitness for Duty Program, in Compliance w/10CFR26 ML20005E3531989-12-28028 December 1989 Forwards Response to Generic Ltr 89-10 Re safety-related motor-operated Valve Testing & Surveillance.Util Intends to Extend Existing IE Bulletin 85-003 Program to Cover motor- Operated Valves within Scope of Ltr ML20005E3191989-12-28028 December 1989 Responds to Violations Noted in Insp Rept 50-271/89-17 on 890906-1016.Corrective Actions:Plant Procedures Revised & Addl Meetings Between Plant Manager,Dept Supervisors & Personnel to Take Place ML19332G1791989-12-12012 December 1989 Forwards Rev 0 to Vermont Yankee Nuclear Power Station Cycle 14 Core Operating Limits Rept. ML19332F2781989-11-30030 November 1989 Forwards Rev 1 to YAEC-1693, Application of One-Dimensional Kenetics to BWR Transient Analysis Methods, Per 891106 Ltr.Rept Presents Methodology,Verification & Justification for Application of RETRAN-02 One Dimensional Option ML19332E3511989-11-29029 November 1989 Forwards Annual Cashflow Statements for 1989 as Evidence of Util Maint of Approved Guarantee,Per Requirements of 10CFR140.21 Re Licensee Guarantees of Payment of Deferred Premiums ML19332E5281989-11-28028 November 1989 Requests Removal of Change B to Proposed Change 148 Re Rev to Pages 5b & 6a Correcting Administrative Error in Tech Spec 2.1 ML19332D3801989-11-22022 November 1989 Responds to NRC Generic Ltr 89-21 Re Request for Info Re Status of Implementation of USI Requirements.Encl Table Details Implementation Status for USIs for Which Final Technical Resolution Achieved ML19324C1501989-11-10010 November 1989 Responds to NRC Bulletin 88-010,Suppl 1 Re Molded Case Circuit Breakers.Program Initiated to Ensure That Breakers Can Perform Safety Functions ML19324C2201989-11-0606 November 1989 Requests Change in Review & Approval Basis from Facility Specific to Generic Because Methods Described in YAEC-1693 & YAEC-1694 Applicable to All BWRs ML19325F0261989-11-0606 November 1989 Responds to Generic Ltr 89-07, Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs. Util Has Evaluated Listed Considerations,Including Safe Standoff Distances for Vital Equipment ML19324B7431989-10-30030 October 1989 Responds to Generic Ltr 89-16 Re Installation of Hardened Wetwell Vent.Util Expects to Establish Specific Design Criteria to Install Enhanced Containment Overpressure Protection Capability by End of 1992 Refueling Outage ML19324B8481989-10-30030 October 1989 Provides NRC W/Test Acceptance Criteria for Alternate Test of CO2 Suppression Sys,Per 891025 Meeting.Ability to Contain CO2 at Appropriate Concentration for Required Duration,As Well as Ability to Withstand Dynamics of Discharge,Verified 1990-09-10
[Table view] |
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VERMONT YANKEE NUCLEAR POWER CORPORATION
. RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 Ygg8f11 y -
ENGINEERING OFFICE 1671 WORCES TER ROAD
' TELEPHONE 817-872-8100 January 31, 1985 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Office of Nuclear Reactor Regulation Mr. D.G. Eisenhut, Director Division of Licensing
References:
a) -License No. DPR-28 (Docket No. 50-271) b) Letter, VYNPC to USNRC, FVY 84-34, dated 4/11/84 c) Letter, VYNPC to USNRC, FVY 84-74, dated 6/29/84 d) Letter, VYNPC to USNRC, FVY 84-81, dated 7/10/84 e) Letter, VYNPC to USNRC, FVY 84-90, dated 7/19/84 f) Letter, VYNPC to USNRC, FVY 84-92, dated 7/25/84 g) Letter, USNRC to VYNPC, NVY 84-179, dated 8/2/84 h) Letter, VYNPC to'USNRC, FVY 84-98, dated 8/10/84 i) Letter, VYNPC to USNRC, FVY 84-127, dated 10/30/84 j) letter, USNRC to VYNPC, NVY 84-263, dated 12/12/84 k) Letter, USNRC to All Licensees of Operating Reactors, (Generic Letter 84-24) NVY 84-268, dated 12/27/84 l) . Letter, USNRC to VYNPC, NVY 83-75, dated 4/11/83
Dear Sir:
Subject:
Certification of Compliance to 10CFR50.49, Environmental Qualification of Electric-Equipment Important to Safety for Nuclear Power Plants (Generic Letter No. 84-24)
~
By Generic Letter No. 84-24 [ Reference k)] and pursuant to 10CFR50.54(f),
you requested that each licensee of an operating reactor submit a Certification of Compliance to 10CFR50.49, Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants. This letter provides Vermont Yankee Nuclear Power Corporation's (VYNPC) response to that request.
Specifically, you requested certification that:
_, hO L
B502060130 850131 3 DR ADOCK 0500027}
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.- 1U.S.; Nuclear Rsgulatory Commission January 31, 1985 Page 2 VERMONT YANKEE NUCLEAR POWER CORPORATION 3
2 5.
o The utility;has in place and is implementing an Environmental a)_
Qualification (EQ) Program that will satisfy the requirements of *
>: 10CFR50.49 within the currently approved schedule for the plant
.g without -further extension; b) The plant has at least one path to safe shutdown using fully qualified equipment, or has submitted a Justification for Continued Operation (JCO) pending full qualification of any equipment not fully qualified; and c) ~ All other equipment' within the scope of 10CFR50.49 is either fully qualified or a JC0 has been submitted pending full qualification.
You'further requested that the certifications described in References a),
b) and c) above should specifically address all IE Bulletins and Information
. Notices that identify EQ problems, to the extent that 'such Bulletins and Notices are:relevantito the licensee's facility. You considered the following ~ Bulletins ;
. and Information Notices . applicable to these certifications: IE Bulletin 82-04,
~ '
'IE1Information. Notices 82-11, 82-52, 83-45, 83-72, 84-23, 84-44, 84-47, 84-57, J 84-68 and'84-78.
- With respect to certifying .a), b) and c) above, Vermont Yankee has submitted
.a . comprehensive; upgraded program for ensuring . environmental qualification of safety-related electrical equipment in accordance with the provisions of.
- 10CFR50.49.; .The details:of our-Environmental Qualification Program (EQP) are Ldescribed in References b), c),.d), e), f) and:g). The NRC . subsequently. issued a
? Safety Evaluation Report.(SER) dated December 12, 1984 [ Reference j)],-which concluded.that'the_ Vermont- Yankee EQP was in compliance with the requirements of u 10CFR50.49;1that the ' proposed resolution; for Leach of the'_ environmental qualifi-cation deficiencies identified in'the April. 11, 1983 Franklin Research1 Center
- Technical Evaluation; Report' [ Reference 1)] was ' acceptable; and, the continued Loperation ofithe. Vermont' Yankee Nuclear Power. Station would not present undue
_1 riskf to publie health and safety.
nBylletter dated-July 25,L1984, we(request'ed an extension from the 'schedu -
l ;1.ar3 requiremen.ts .of: 10CFR50.49(g) for: replacement oftcertain _ equipment that -
~
tg icould not- beLeompleted during.~our: 1984 refueling outage.- Our letter, requested
~
-extensions 1until thefend of theinext refueling outage, which is scheduled to
~ ~
, commence 11niSeptember?1985 and extend.into 1986, and included Justification for
- Continued Operation during theLinterim period.~ The NRC subsequently reviewed-
- and. approved our requests as detailed in.a letter
- to us dated August 2,1984-
'[ Reference g)]; however,-schedularf relief was ' granted until' no later than
- Movember"30,11985L consistent 'with the schedular limitations prescribed-byi
'10CFR50.49(g).
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. . U.S. Nuclear Regulatory Commission January 31, 1985 Page 3 VERMONT YANKEE NUCLEAR POWER CORPORATION We will replace all equipment identified as requiring environmental quali-fication which is not presently fully qualified, as identified in Enclosure 1, during our next outage, scheduled to extend from September 1985 into 1986. Due to the schedule of work associated with this outage, we cannot assure that the remaining components will be replaced by November 30, 1985. Therefore, we will be submitting a formal request for schedular relief to the Commissioners to complete the remaining component upgrades no later than start-up from our 1985 pipe replacement / refueling outage. This extension request will be submitted by
- March 1, 1985. _The additional time is justified given that the plant will be in a refuel mode and no potential harsh environmental conditions exist until startup '
.. in 1986. 1 It should also be noted that the list of yet to be qualified electrical l components provided in the NRC's December 12, 1984 SER was inaccurate. First, the _SER did not .!st certain ASCO Solenoid Operated Valves which were included in our July 25, IC84 extension request and approved in the NRC's August 2,1984 response: letter. Second, the SER incorrectly lists MOV-12-15. As listed in our July _25, 1984 request, the correct component tag number is M0V-13-15. Finally, the scope of our JDly 25, 1984 request reflected certain co.rpeneats taat were subsequently replaced during' ti e 1964 refuel ' outage with qualified counterparts.
At the time of our request we were unsure as to whether the qualified replace-ments would be received on-site in time to be installed during that. outage. As a result, we have updated the list provided in the SER to accurately reflect the remaining components that need to be replaced at Vermont Yankee. This list is
- provided in Enclosure 1 and includes a reference to the associated JCO.
r In _ addition to the electrical equipment covered under the scope of the b . Vermont Yankee E0P, we have recently completed our Regulatory Guide (RG) 1.97
- assessment which is1one, facet of our Integrated Response Plan for NUREG 0737, Supplement I, Emergency Response Capability. _A report' detailing our assessment.
was provided to the NRC by letter dated October 30, 1984 [ Reference 1)] and is cur'rently under review. As stated in our submittal, it is our present intent to
' upgrade certain RG 1.97 instrumentation which fall within the senpe of
, 10CFR50.49,- prior to startup fran;our 1985 refuel outage. The NRC's December
-12, 1984 SER for Envirenmental Qualification acknowledges the ongoing review of -
- our submittal and states that when the RG-1.97 report and equipment lists con-
- tained therein have been finalized and accepted by the' staff, anpropriate equip-
- ment not already in 10CFR50.49 will be added in accoadance 51th the RG 1.97
- implementation schedule. It should be noted th&c our current' schedule for. the EQ-related components is predicated on our timely receipt of the NRC's approval
- of our RG 1.97 assessment, such that sufficient- time exists to order necessary
--replacement components in time for our 1985 refuel outage.
4
- .- . d.S;JNucleariRegulatory Commission
.lanuary 31, 1985
'Page 4 VERMONT YANKEE NUCLEAR POWER CORPORATION LAll components required as part of our upgraded EQP were fully qualified upon startup from our 1984 refueling outage [ consistent with the schedular pro-visions of 10CFR50.49(g)] except for the components listed in Enclosure 1. Once
- the ASCO Solenoid Valves (component Tag Nos. SE-70-4A, 4B,14C and 4D) listed in the. Enclosure are fully qualified, Vermont Yankee will have at least one path to-achieve safe shutdown using fully qualified equipment. In the interim the JC0's referenced in Enclosure 1, which have been reviewed and approved by the NRC, ensure'that'we satisfy the intent of 10CFR50.49.
Vermont Yankee has administrative controls in place to address instances c where any component required by our EQP becomes inoperable, or when plant designLfeatures1necessary to maintain environmental conditions (e.g., doors, shielding, fans, etc.) are degraded.
i
- Vermont Yankee has' conducted a thorough review of the I&E Eulletins and -
LInformation Notice: referenced-above. .The summary results of our review of each
- - ;of the notifications is; providedlin Enclosure 2. . We will continue to review and
- f assess. the results of- future I&E Bulletins and Information Notices related. to
. environmental qualification. Where applicable, we will, factor the results of.
,our assessment into our Environmental Qualification Program.
~
To~ ensure ' designated environmentally qualified ~ equipment is properly main-tained' through the expected life ~of that equipment, and that any. change to the
. expected life 11s recognized and compensated for programmatically, we expanded t our' Maintenance 'and -Surveillance . Program to ' provide specific . identification of
, Environmentally; Qualified- Equipment, ~as' described in' our letter dated August'10, E , :1984-[ Reference h)]. Vermont: Yankee is presently fo'rmulating a dynamic, t integrated' Environmental' Qualification Maintenance and Surveillance Program that
~
will-provide the necessary. control to maintain user department-component files pgs '
Lcurrent.and a'ccurate. Component ~ file completion,; review and approval of proce-
^
idures 'and fu111 implementation will Jbe completed approximately: 90 days following lfinaiization of'the controlled-source documents which is scheduled for March
- 1385. During this transitional period, the existing Maintenance and ,
E- ' Surveillance-process, augmented by interim administrative actions to meet the intent Lof ~10CFR50.49(d), will ' continue to be utilized.
- Based onLthe.above,-Vermont Yankee Nuclear Power Corporation.herein cer-
, [i fies .that:-
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. di
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v.
U.S. Nuclear Rzgulatory Commission
. January _31, 1985 Page 5 VERMONT YANKEE NUCLEAR POWER CORPORATION a) Vermont Yankee f.23 in place and is implementing an Environmental Qualification Program (EOP) that will satisfy the requirements of 10CFR50.49, as described in References b), c), d), e), f) and g) except that:
- 1) the schedule for completing our remaining component upgrades is no later than startup from our 1985 pipe replacement / refuel outage, which is later than the November 30, 1985 deadline pro-vided.in the August 2, 1984 NRC letter approving extension requests. As discussed above, a formal request for additional schedular relief will be submitted to the Commissioners by March p 1,.1985.
- 2) the schedule for completing RG 1.97 EQ-related component upgrades
, is dependent upon the NRC's approval of c w RG 1.97 assessment report in a timely manner.
.The schedules detailed in 1) and 2) assume no unforseen difficulties in the procurement and installation of necessary replacement com-ponents or the receipt of associated vendor qualification
_ documentation.
b) The plant will have at least one path to achieve safe shutdown using fully qualified equipment once the' ASCO Solenoid Valves (Component Tag Nos. SE-70-4A, 4B, 4C and 4D)' listed in Enclosure 1 have been qualified. A JC0 for these valves was submitted as part of our July 25, 1984 request for. schedular extension and approved by the NRC as
. described in their letter-dated August 2,1984.
c) All other equipment within the scope of 10CFR50.49, as described in our upgraded EQP, was fully qualified upon startup from our-1984 refueling outage except for those components listed in Enclosure -1.
JC0's for these components were submitted as part of our July 25, 1984 request for schedular extension and approved by the NRC as described in their. letter dated August 2, 1984.
Finally, as statediin previous submittals, our Environmental Qualification Program is an ongoing and evolving program. Future facility design modifica-tions will be evaluated to assure that their impact, if any, is adequately reflected in' our program. In addition, as we become aware.of any engineering
r;
,. . U.S. _ Nuclear Regulatory Commission January 31, 1985 Pag; 6 VERMONT YANKEE NUCLEAR POWER CORPORATION information (e.g., vendor information, NRC I8E Bulletins and Information Notices,. engineering analyses, etc.) which could putentially impact particular aspects of our program, such information will also be evaluated to determine if programmatic changes are warranted.
We trust that this information is deemed _ satisfactory; however, should you have any questions or desire additional information, please contact us.
Very truly yours, VERMONT YANKEE NLCt. EAR POWER CORPORATION f$
Warren P.' Murphy h
f Vice President and V Manager of Operations WPM /dm' STATE ~0F VERMONT)
)ss WINDHAM COUNTY' )
. _Then personally appeared before me, Warren P.. Murphy, who, being duly
- sworn, did state that he'is Vice President and Manager of Operations of Vermont
' Yankee Nuclear Power Corpo' ration,:that_ he is duly authorized to execute and file the' foregoing document in the name and _on the behalf of Vermont Yankee Nuclear
" Power Corporation and that the statements therein are true to the best of his knowled a belief.
7 fs 5 j lG Diane M. McCue ' Notary Public
-My Commission Expires February 10, 1987 NOTARY l
\,COUNU/
Q
7 ENCLOSURE 1 JUSTIFICATION FOR CONTINUED OPERATION EQUIPMENT LIST JC0 NO. DESCRIPTION 29- General Electric Control Rod Drive Mechanism (Position Indication, Switches, Cables, and un Conncetors) 39'- General Electric Local Power Range Monitor System (Neutron Detectors, Indication, Cables, and
- i. Electrical Connections) 14 3 - Limitorque SMB-00 Assembly for M0V-10-32 (RHR Head Spray Isolation) 46 Limitorque SMB-000 Motor for MOV-13-15 (RCIC
, Inboard Steam Isolation)
.69- Limitorque SMB-0-Motor for MOV-10-39A (RHR "A" Torus Cooling and Spray Outboard Isolation) 66 ASCO Solenoid Operated Valves,' SE-70-4A, 4B, 4C and 4D (Residual Heat-Removal ~ Service Water Cooling)
T f .i ?
b ..
. . ENCLOSURE 2
SUMMARY
OF VERMONT YANKEE'S ASSESSMENT OF EQ RELATED BULLETINS AND INFORMATION NOTICES 18E BULLETIN 82-04 Vermont Yankee.has no Bunker Ramo electrical penetrations. Further, there are no plans to install any in safety-related systems in the future.
IAE INFORMATION NOTICE 82-52
= This Notice addressed the items of equipment discussed below:
Limitorque Valve Operator, Type SMB, Size 00: The failure reported in this Information Notice is attributed to the severe requirement imposed by the Westinghouse PWR temperature profile. Vermont Yankee does not . consider this Notice applicable to the Limitorque Valve Operators installed in BWR's where the temperature profile is less severe.
-ITT Barton Westinghouse lot 4 Transmitters, Group A: Vermont Yankee does not utilize these transmitters in applications which are required to meet the . Environmental Qualification Rule. .
D.G. O'Brien Electrical Penetration Assembly, Model K Connectors:
~
Vermont . Yankee does not utilize this equipment in applications which are required to meet the Environmental Qualification Rule.
Dresser Safety Valve, Model 31709NA: Vermont Yankee does not utilize this equipment in applications which are required to meet the Environ-mental Qualification Rule.
Dresser' Safety Valve, Model 31739A:1 Vermont Yankee does not utilize this equipment in-applications which are required .to meet-the Environ-L mental-Qualification Rule.
, Dresser Power-Operated Relief. Valve (PORV), Model 31533VX-30: Vermont
- , Yankee does not utilize this equipment in applications which are required to meet the Environmental Qualification Rule.-
Target Rock Power-Operated Relief Valve'(POR'V)~, Model B0X-006-1:
Vermont-Yankee does not utilize this equipment in applications which -
me :,. 'are required to meet the Environmental' Qualification Rule.
-Control Comionents, Inc. (CCI),' Power-Operated Relief Valve (PORV):-
. Vermont Yan cee does not utilize.this equipment in applications which!
- 'are ' required to meet the Environmental Qualification Rule.-
- e. 1 of'5
- e. .,
5Y
Crosby Safety Valve 3K6: Vermont Yankee does not utilize this equip-ment in_ applications which are required to meet the Environmental Qualification Rule.
- ASCO Solanoid Valves, NP-1 Series: Vermont Yankee utilizes ASCO NP-1 Solenoid Valves including those with Viton Elastomer Seals as
. described in the I&E Information Notice. In all cases, these valves have been verified to be located in areas where the radiation environ-
. ment is less than 20 megarads.
, I&E INFORMATION NOTICE 82-11 This Notice' describes potential problems with equipment supplied by
- Westinghouse Electric Corporation to owners of Westinghouse Nuclear Steam Supply Systems. The Vermont Yankee . facility, a General Electric boiling
, water-reactor,.does not utilize Westinghouse instrumentation in applications
- required to _ meet _ the Environmental Qualification Rule.
IAE-INFORMATION NOTICE 83-45 This' Notice deals with failure of. General! Electric Model CR-2940 selector switches following exposure to:37 megarads. Vermont Yankee does not uti-
,lize this model selector switch in any application, required to meet the
.Eny'ironmental. Qualification Rule where it will be subject to radiation doses as'high as 33.5 megards.
IAE:INFORMATION NOTICE 83 The equipment discussed below is listed in this Notice:
Anaconda Flexible Conduit: Vermont Yankee does not use.this equipment to seal qualified equipment from the LOCA' environment.
Rockwell-International Post-LOCA Hydrogen Recombiner (Subcomponents as listed below):-
-o ITT Barton Pressure Transducer', 4-20 mA, Part_No. D4R-29098:
. Vermont Yankee does .not utilize this-equipment in applications which are required to meet'the Environmental Qualification Rule. _
.or .'Microswitch, DPST Toggle Switch, Rated 15A,125-250 V ac,1/2 HP, .
125 V ac,JPart No. 12TSI-2: Vermont Yankee does not utilize this-L' '
equipment in applications which are required to meet the-Environmental -Qualification Rule.- 1 s
- 2 of 5 -
v
.-,.y
n-l
. =. \
o Square D Disconnect Switch, 3 Pole Non-Fusible Unit, 30A, 15 HP at'480 V ac, or 20 HP at 600 V ac, Part No. 9422-RC-1: Vermont
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Yankee does not utilize this equipment in applications which are
- required to meet the Environmental Qualification Rule, j
/o Timetrol SCR Power Controller, 3-Phase,1066Z Series, Part No.
2053C-125K: Vermont Yankee does not utilize this equipment in applications which are required to meet the Environmental Quali-fication Rule.
Jo . Automatic Timing and Control (ATC) Time Delay Relay,120 V ac, 1
50-60 Hz, Part No. 3198006010, IEEE 21A: Vermont Yankee does not utilize this _ equipment in applications which are required to meet the' Environmental Qualification Rule.
Jo ITE Gould Circuit Breaker, 3-Pole, 600 V ac, Fully Enclosed,
-Thermal Magnetic, Part No EF3-8015, IEEE 79: Vermont Yankee does not-utilize this and other Gould circuit breakers in applications which are. required to meet the Environmental Qualification Rule.
Qualification of these circuit breakers is documented in our QDR 3 2.3 ITE/Gould Motor Control Centers. In all cases, the maximum
- accident' temperature for_ Gould circuit breakers is less than
-1160F =and our_ analysis demonstrates-that the breakers will not open under these temperatures.
.ITT Barton Electronic Transmitters:' Vermont Yankee does,not' utilize this equipment in applications which are required to meet the Environ-mental Qualification -Rule'.
- Barksdale Pressure Switches: Those Barksdale pressure switches which were utilized in applications required to meet-the Environmental Qualification Rule were replaced with environmentally qualified switches made by other manufacturers during the 1984 refueling outage.
D -Static-0-Ring' Pressure Switches: Those Model SN and 12N Static-0-Ring Lpressure switches which were utilized in~ applications required to. meet-
- the Environmental Qualification Rule were replaced Lwith environmentally -
qualified -Static-0-Ring pressure switches during the~1984 refueling Loutage.
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ITT'Bartori Electronic Transmitters, Models M'-763 and M-764: Vermont
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Yankee does not utilize this equipment-in applications which are required to meet the. Environmental Qualification Rule.
Limitortue Valve 03eratorsi The concerns'raisedLin this Notice have
- been adt ressed by Jermont Yankee's Equipment Qualification Program.
.The. field verification program and QDR 3.1 Limitorque valve operator -
-addresses the concerns'of this Notice.
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E I&E Information Notice 84-23 This Notice deals with the results of testing conducted by Franklin Research -Center for the NRC and involves some naturally aged ASCO Model NP-8316 and NP-8344 solenoid valves. The Vermont Yankee facility does not utilize the Model NP-8344 valves in applications which are subject to the Environmental Qualification Rule. Those NP-8316 valves utilized in appli-cations subject to the Equipment Qualification Rule have been assessed against~Isomedix AQS Report No. 21678/TR-Rev. A. In all cases, we have
~ found that using the Isomedix Test Report we are able to confirm Environ-mental Qualification of these valves.
IAE~INFORMATION NOTICE 84-44 This Information Notice reports problems with the Rockbestos Company Environmental' Qualification Program. lne problems were discovered during a' NRC audit and all reflect quality assurance and documentation problems during the test process. The concerns do not indicate a deficiency in the equipment. Our qualification files for Rockbestos cable address this Notice. Vermont Yankee and Yankee Atomic Electric Company are _ continuing to_ work with the manufacturer to resolve these apparent concerns.
Rockbestos has_ committed to a program of revalidating their cable qualifi-cation tests. Vermont Yankee is following the progress of this effort and will update the qualification files when the issue is resolved.
IAE INFORMATION NOTICE 84-47 ,
This Notice reports the results of tests conducted by Sandia National Laboratories on various. terminal block installations during simulated steam
- exposure. Leakage current-to-ground was measured _in each test and it was o independent of circuitLvoltage. The tests concluded that terminal blocks in a steam environment may introduce significant error in low level cir-cuits (4-20 ma), such that the safety' function is jeopardized.
- Vermont Yankee has reviewed the application of all terminal blocks and has
- documented in our files that the blocks are either not used in ' low level circuits or errors introduced as a result of leakage currents would have no
'effect on the safety function.
L I&E INFORMATION NOTICE 84-57 ,
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This Notice alerts licensees:of a potentially significant problem per-taining to moisture intrusion into_ safety-related equipment. Vermont Yankee's Equipment Qualification Program considered the concerns of:this
. Notice by:
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- 1) addressing cable / raceway sealing requirements in the qualification documents; 2). performing a Field Verification Program which ensured' that conduit seals and gaskets were installed when required; and
.3) addressing moisture sealing requirements in the Maintenance and Surveillance Program.
I&E Information Notice 84-68 This Notice deals with damage to. field cable connected to Valcor solenoid valves. The cause of the failure was the use of 900C cable connected inside the valve housing which was subjected to higher temperatures
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. generated tyr the solenoid coil . At the Vermont Yankee facility, the only solenoid. valves utilized in applications required to meet the Environmental Qualification Rule which have field terminations inside the solenoid housing are Target Rock valves. We have discussed this matter with. Target Rock and have determined that the temperatures inside the housing where the terminations are made do.not reach temperatures which exceed the qualifica-tion of-the cable utilized.
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I&E Information Notice 84-78 LThis Notice deals with underrated terminal blocks in Limitorque Model SMC-04 valve' actuators. Vermont Yankee does not utilize this equipment in
- applications 'which are required to meet the Environmental Qualification
, Rule.:
, 'VermontiYankee will continue to review and assess-the results ofifuture I&E Bulletins and -Information Notices.related to environmental nualification. .Where -
' applicable, we will ' factor the results of these'into our Environmental Qualifi-cation Program..
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