|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N3901999-10-25025 October 1999 Advises That Info Provided in & Affidavit Re Holtec Position Paper WS-115,rev 1,repts HI-87113, Rev 0,HI-87114,rev 0,HI-87102 Rev 0 & HI-87112,rev 0,marked Proprietary,Will Be Withheld from Public Disclosure ML20217L8591999-10-21021 October 1999 Discusses 990921 Request for Approval to Perform Alternative Testing as Part of Vermont Yankee Nuclear Power Station IST Program.Informs That Submittal Reviewed Against ASME Code Section XI Requirements & Forwards Safety Evaluation ML20217M1181999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20217D9711999-10-13013 October 1999 Responds to Request That Information Titled Addl Info Re Cycle Specific SLMCPR for Vermont Yankee Cycle 21 Be Withheld from Public Disclosure.Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20217F1261999-10-12012 October 1999 Forwards Update to Previously Submitted RELAP5 Analytical Assumptions for App R,Re RAI of 961104 BVY-99-130, Provides Clarification of Method for Determining MSIV Maximum & Minimum Pathway at Vermont Yankee Nuclear Power Station1999-10-0808 October 1999 Provides Clarification of Method for Determining MSIV Maximum & Minimum Pathway at Vermont Yankee Nuclear Power Station ML20217C1501999-10-0707 October 1999 Forwards Insp Rept 50-271/99-11 on 990809-27.No Violations Noted.Insp Focused on Effectiveness of Engineering Functions in Providing for Safe Operation of Plant BVY-99-128, Submits Listed Addl Info in Support of 990414 Request for Clarification to SER Confirming Adequacy of Space Cooling for HPCI & RCIC Sys,Re Item II.K.3.24 of NUREG-0737.Copy of NEDE-24955,encl1999-10-0606 October 1999 Submits Listed Addl Info in Support of 990414 Request for Clarification to SER Confirming Adequacy of Space Cooling for HPCI & RCIC Sys,Re Item II.K.3.24 of NUREG-0737.Copy of NEDE-24955,encl ML20212J7891999-10-0404 October 1999 Informs That Licensee 980804,0628,29 & 990921 Responses to GL 98-01, Y2K Readiness of Computer Sys at NPPs Acceptable.Nrc Consider Subj GL to Be Closed for Plant ML20212J6501999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of VYNPS on 990913. No New Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues & Insp Plan Through Mar 2000 Encl ML20216J3531999-09-29029 September 1999 Responds to NRC Re Violations Noted in Insp Rept 50-271/99-12 on 990628-0811.Corrective Actions:Based on RFO 20 Maint Rule Outage Performance Review,Task Was Generated to Clarify & Enhance SD Monitoring Process BVY-99-122, Notifies of Intention to Reinstate Original Version of App F in FSAR & Correct Docket Re Assumption That Electrical Power Sys Are Designed IAW Requirements of GDC-171999-09-28028 September 1999 Notifies of Intention to Reinstate Original Version of App F in FSAR & Correct Docket Re Assumption That Electrical Power Sys Are Designed IAW Requirements of GDC-17 BVY-99-114, Provides Notification That Licensee Completed Y2K Remediation Efforts Described in Util 990608 Response to NRC GL 98-01,Suppl 11999-09-21021 September 1999 Provides Notification That Licensee Completed Y2K Remediation Efforts Described in Util 990608 Response to NRC GL 98-01,Suppl 1 BVY-99-113, Requests Approval to Perform Alternative Testing to That Specified by ASME Boiler & Pressure Vessel Code,Section XI & Asme/Ansi OM, Operation & Maint of Nuclear Power Plants. Attachment 1 Provides Justification for Alternative Testing1999-09-21021 September 1999 Requests Approval to Perform Alternative Testing to That Specified by ASME Boiler & Pressure Vessel Code,Section XI & Asme/Ansi OM, Operation & Maint of Nuclear Power Plants. Attachment 1 Provides Justification for Alternative Testing BVY-99-116, Informs of Determination That Wh Schulze,License SOP-10528-1,will No Longer Maintain License at Facility. Termination of License Requested1999-09-21021 September 1999 Informs of Determination That Wh Schulze,License SOP-10528-1,will No Longer Maintain License at Facility. Termination of License Requested BVY-99-121, Requests Extension Until 990929 to Respond to Violations Noted in Insp Rept 50-271/99-12,dtd 990819.Licensee Did Not Receive Rept Until 990830 & Addl Time Is Needed to Prepare & Allow for Adequate Review of Violation Response Submittal1999-09-20020 September 1999 Requests Extension Until 990929 to Respond to Violations Noted in Insp Rept 50-271/99-12,dtd 990819.Licensee Did Not Receive Rept Until 990830 & Addl Time Is Needed to Prepare & Allow for Adequate Review of Violation Response Submittal ML20212C1621999-09-17017 September 1999 Forwards Amend 175 to License DPR-28 & Safety Evaluation. Amend Revises TSs to Enhance Limiting Conditions for Operation & Surveillance Requirements Relating to Standby Liquid Control System BVY-99-118, Responds to RAI Concerning GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions1999-09-16016 September 1999 Responds to RAI Concerning GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions BVY-99-115, Forwards non-proprietary & Proprietary Responses to 990714 RAI Re Civil & Mechanical Engineering Considerations for Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355.Proprietary Encls Withheld1999-09-16016 September 1999 Forwards non-proprietary & Proprietary Responses to 990714 RAI Re Civil & Mechanical Engineering Considerations for Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355.Proprietary Encls Withheld ML20216F3171999-09-13013 September 1999 Forwards Insp Rept 50-271/99-06 on 990621-0801.One Violation Identified & Being Treated as Noncited Violation BVY-99-110, Informs of Util Intent to Replace Commitments Made in Licensee & Subsequently Ack in NRC with Containment Insp Criteria Defined in 10CFR50.55a(b)(2)(vi),per Drywell Coating Insp1999-08-31031 August 1999 Informs of Util Intent to Replace Commitments Made in Licensee & Subsequently Ack in NRC with Containment Insp Criteria Defined in 10CFR50.55a(b)(2)(vi),per Drywell Coating Insp BVY-99-111, Informs That Encl TS Bases Page 91 Has Been Revised to Allow Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line Uncorrected Solution & on-line 3D-Monicore Exposure Corrected Solution1999-08-31031 August 1999 Informs That Encl TS Bases Page 91 Has Been Revised to Allow Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line Uncorrected Solution & on-line 3D-Monicore Exposure Corrected Solution ML20211G4791999-08-27027 August 1999 Forwards Notice of Withdrawal of 990420 Amend Request Re TS on Reloading & Unloading Sequence of Fuel in Reactor Core When All Fuel Removed from Core BVY-99-107, Submits Response to NRC RAI Re Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355 Fuel Assemblies1999-08-26026 August 1999 Submits Response to NRC RAI Re Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355 Fuel Assemblies ML20211E8841999-08-25025 August 1999 Requests That Licensee Provide bldg-specific Justification for Use of Method A.1 at Locations Where Amplification Significantly Exceeds 1.5 Limit Above 8 Hz ML20211E1371999-08-20020 August 1999 Forwards from J Bean to H Miller & FEMA Final Exercise Rept for 990427-29 Plume Exposure & Ingestion Pathway Exercise for Vermont Yankee Nuclear Power Station.No Deficiencies Noted.Areas Requiring C/A Identified ML20211H0851999-08-19019 August 1999 Forwards Insp Rept 50-271/99-12 on 990628-0711 & Nov. Violation Re Failure to Monitor Unavailability of Specific Sys,Structures & Components During Refueling Outage Did Not Allow Adequate Assessment of Maint Effectiveness BVY-99-108, Requests That Gv Bogue,Bj Croke,Vs Ferrizzi,Me French, Bk Mcnutt,Jf Meyer & DM Navarro Take BWR Gfes of OL Exam Administered on 991006.DA Daigler & ST Brown Will Have Access to Exams Before Tests Administered1999-08-19019 August 1999 Requests That Gv Bogue,Bj Croke,Vs Ferrizzi,Me French, Bk Mcnutt,Jf Meyer & DM Navarro Take BWR Gfes of OL Exam Administered on 991006.DA Daigler & ST Brown Will Have Access to Exams Before Tests Administered BVY-99-103, Informs That Util Expects to Submit Approx Twenty Licensing Actions in FY00 & FY01,in Response to Administrative Ltr 99-021999-08-18018 August 1999 Informs That Util Expects to Submit Approx Twenty Licensing Actions in FY00 & FY01,in Response to Administrative Ltr 99-02 BVY-99-100, Forwards Revised Floor Response Spectra Diagrams,Originally Sent as Attachment 1 to Licensee to Nrc.Revised Diagrams Have More Legible Scale Markings1999-08-0202 August 1999 Forwards Revised Floor Response Spectra Diagrams,Originally Sent as Attachment 1 to Licensee to Nrc.Revised Diagrams Have More Legible Scale Markings ML20210M5791999-07-30030 July 1999 Responds to NRC 990726 Telcon Re Status of Resolution for USI A-46 Outliers.Written Summary,By Equipment Category, Listed ML20211E1701999-07-28028 July 1999 Forwards Copy of Final Exercise Rept for 990427-29,full- Participation Plume Exposure & Ingestion Pathway Exercise of Offsite Radiological Emergency Response Plans site-specific to VYNPS ML20210G5041999-07-27027 July 1999 Responds to NRC 990301 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions. Licensee Will Submit Info Re Proposed Sys Mod by 990916 ML20210J3031999-07-27027 July 1999 Submits Proposed Changes to Eals.Attachment 1 Provides Listing of Changes to EALs Along with Ref to Bases Documents Supporting Change ML20210G4271999-07-27027 July 1999 Forwards Testing Data & Associated Results for Fitness for Duty Program at Plant for 990101-0630 ML20216D7321999-07-26026 July 1999 Forwards Insp Rept 50-271/99-05 on 990510-0620.Two Viiolations Being Treated as Noncited Violations ML20209G2721999-07-14014 July 1999 Discusses Licensee Response to RAI Re GL 92-01,Rev 1,Suppl Suppl 1, Rv Structural Integrity, for Vermont Yankee Nuclear Power Station ML20209J0601999-07-14014 July 1999 Forwards Rev 11 to Vols 1-10 of State of Nh Radiological Emergency Response Plan & Vols 11-50 to Town Radiological Emergency Response Plans,In Support of Vermont Yankee & Seabrook Station.Vols 17-19 of Were Not Included ML20209G6931999-07-14014 July 1999 Forwards Request for Addl Info Re Spent Fuel Storage Capacity Expansion ML20209G1531999-07-12012 July 1999 Discusses Util Setpoint Control Program Implementation Schedule,As Committed to in Licensee 990514 Response to Notice of Violation,Insp Rept 50-271/97-10 ML20196J2321999-06-30030 June 1999 Submits Input from Util Technical Staff Re Soil Disposal on-site Under 10CFR20.2002 & Expresses Interest in Pursuing Approval to Use Same Methodology (Implemented Through Util ODCM & Reported as Noted) If Possible ML20196J7421999-06-29029 June 1999 Informs NRC That Vygs Has Implemented Severe Accident Management,As Committed to in Licensee to NRC ML20209B6111999-06-29029 June 1999 Resubmits Summary of Vynp Commitments Page to Replace Original Page Submitted with Responding to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20196J2431999-06-29029 June 1999 Informs That Author Received Call from NRR on Dirt Spreading Ltr & Questions Re Cover Ltr Statement Where Util Asks to Be Allowed to Dispose of Future Soil in Same Manner Provided Same Acceptance Criteria Met ML20209C3751999-06-28028 June 1999 Forwards non-proprietary Rev 16 to EPIP OP 3524, Emergency Actions to Ensure Initial Accountability & Security Response & Proprietary Rev 12 to EPIP OP 3531, Emergency Call-In Method. Proprietary Encl Withheld ML20209B5861999-06-28028 June 1999 Provides Alternative Y2K Readiness Status Described in Supplement 1 to GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure Rept Encl ML20196G5241999-06-22022 June 1999 Responds to Re Changes to Vermont Yankee Guard Training & Qualification Plan,Rev 8,Errata A.No NRC Approval Is Required.Encl Will Be Withheld from Public Disclosure Per 10CFR73.21 BVY-99-084, Forwards Proprietary Application & Medical Certificate for Mod of Listed SRO License,For Gj Leclair.Gj Leclair Will Be Trained & Evaluated in Accordance with Util Lsro Training Description.Proprietary Info Withheld,Per 10CFR2.7901999-06-18018 June 1999 Forwards Proprietary Application & Medical Certificate for Mod of Listed SRO License,For Gj Leclair.Gj Leclair Will Be Trained & Evaluated in Accordance with Util Lsro Training Description.Proprietary Info Withheld,Per 10CFR2.790 ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20195H1741999-06-15015 June 1999 Forwards Original & Copy of Request for Approval of Certain Indirect & Direct Transfer of License & Ownership Interests of Montaup Electric Co (Montaup) with Respect to Nuclear Facilities Described as Listed 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217F1261999-10-12012 October 1999 Forwards Update to Previously Submitted RELAP5 Analytical Assumptions for App R,Re RAI of 961104 BVY-99-130, Provides Clarification of Method for Determining MSIV Maximum & Minimum Pathway at Vermont Yankee Nuclear Power Station1999-10-0808 October 1999 Provides Clarification of Method for Determining MSIV Maximum & Minimum Pathway at Vermont Yankee Nuclear Power Station BVY-99-128, Submits Listed Addl Info in Support of 990414 Request for Clarification to SER Confirming Adequacy of Space Cooling for HPCI & RCIC Sys,Re Item II.K.3.24 of NUREG-0737.Copy of NEDE-24955,encl1999-10-0606 October 1999 Submits Listed Addl Info in Support of 990414 Request for Clarification to SER Confirming Adequacy of Space Cooling for HPCI & RCIC Sys,Re Item II.K.3.24 of NUREG-0737.Copy of NEDE-24955,encl ML20216J3531999-09-29029 September 1999 Responds to NRC Re Violations Noted in Insp Rept 50-271/99-12 on 990628-0811.Corrective Actions:Based on RFO 20 Maint Rule Outage Performance Review,Task Was Generated to Clarify & Enhance SD Monitoring Process BVY-99-122, Notifies of Intention to Reinstate Original Version of App F in FSAR & Correct Docket Re Assumption That Electrical Power Sys Are Designed IAW Requirements of GDC-171999-09-28028 September 1999 Notifies of Intention to Reinstate Original Version of App F in FSAR & Correct Docket Re Assumption That Electrical Power Sys Are Designed IAW Requirements of GDC-17 BVY-99-113, Requests Approval to Perform Alternative Testing to That Specified by ASME Boiler & Pressure Vessel Code,Section XI & Asme/Ansi OM, Operation & Maint of Nuclear Power Plants. Attachment 1 Provides Justification for Alternative Testing1999-09-21021 September 1999 Requests Approval to Perform Alternative Testing to That Specified by ASME Boiler & Pressure Vessel Code,Section XI & Asme/Ansi OM, Operation & Maint of Nuclear Power Plants. Attachment 1 Provides Justification for Alternative Testing BVY-99-114, Provides Notification That Licensee Completed Y2K Remediation Efforts Described in Util 990608 Response to NRC GL 98-01,Suppl 11999-09-21021 September 1999 Provides Notification That Licensee Completed Y2K Remediation Efforts Described in Util 990608 Response to NRC GL 98-01,Suppl 1 BVY-99-116, Informs of Determination That Wh Schulze,License SOP-10528-1,will No Longer Maintain License at Facility. Termination of License Requested1999-09-21021 September 1999 Informs of Determination That Wh Schulze,License SOP-10528-1,will No Longer Maintain License at Facility. Termination of License Requested BVY-99-121, Requests Extension Until 990929 to Respond to Violations Noted in Insp Rept 50-271/99-12,dtd 990819.Licensee Did Not Receive Rept Until 990830 & Addl Time Is Needed to Prepare & Allow for Adequate Review of Violation Response Submittal1999-09-20020 September 1999 Requests Extension Until 990929 to Respond to Violations Noted in Insp Rept 50-271/99-12,dtd 990819.Licensee Did Not Receive Rept Until 990830 & Addl Time Is Needed to Prepare & Allow for Adequate Review of Violation Response Submittal BVY-99-115, Forwards non-proprietary & Proprietary Responses to 990714 RAI Re Civil & Mechanical Engineering Considerations for Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355.Proprietary Encls Withheld1999-09-16016 September 1999 Forwards non-proprietary & Proprietary Responses to 990714 RAI Re Civil & Mechanical Engineering Considerations for Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355.Proprietary Encls Withheld BVY-99-118, Responds to RAI Concerning GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions1999-09-16016 September 1999 Responds to RAI Concerning GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions BVY-99-110, Informs of Util Intent to Replace Commitments Made in Licensee & Subsequently Ack in NRC with Containment Insp Criteria Defined in 10CFR50.55a(b)(2)(vi),per Drywell Coating Insp1999-08-31031 August 1999 Informs of Util Intent to Replace Commitments Made in Licensee & Subsequently Ack in NRC with Containment Insp Criteria Defined in 10CFR50.55a(b)(2)(vi),per Drywell Coating Insp BVY-99-111, Informs That Encl TS Bases Page 91 Has Been Revised to Allow Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line Uncorrected Solution & on-line 3D-Monicore Exposure Corrected Solution1999-08-31031 August 1999 Informs That Encl TS Bases Page 91 Has Been Revised to Allow Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line Uncorrected Solution & on-line 3D-Monicore Exposure Corrected Solution BVY-99-107, Submits Response to NRC RAI Re Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355 Fuel Assemblies1999-08-26026 August 1999 Submits Response to NRC RAI Re Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355 Fuel Assemblies BVY-99-108, Requests That Gv Bogue,Bj Croke,Vs Ferrizzi,Me French, Bk Mcnutt,Jf Meyer & DM Navarro Take BWR Gfes of OL Exam Administered on 991006.DA Daigler & ST Brown Will Have Access to Exams Before Tests Administered1999-08-19019 August 1999 Requests That Gv Bogue,Bj Croke,Vs Ferrizzi,Me French, Bk Mcnutt,Jf Meyer & DM Navarro Take BWR Gfes of OL Exam Administered on 991006.DA Daigler & ST Brown Will Have Access to Exams Before Tests Administered BVY-99-103, Informs That Util Expects to Submit Approx Twenty Licensing Actions in FY00 & FY01,in Response to Administrative Ltr 99-021999-08-18018 August 1999 Informs That Util Expects to Submit Approx Twenty Licensing Actions in FY00 & FY01,in Response to Administrative Ltr 99-02 BVY-99-100, Forwards Revised Floor Response Spectra Diagrams,Originally Sent as Attachment 1 to Licensee to Nrc.Revised Diagrams Have More Legible Scale Markings1999-08-0202 August 1999 Forwards Revised Floor Response Spectra Diagrams,Originally Sent as Attachment 1 to Licensee to Nrc.Revised Diagrams Have More Legible Scale Markings ML20210M5791999-07-30030 July 1999 Responds to NRC 990726 Telcon Re Status of Resolution for USI A-46 Outliers.Written Summary,By Equipment Category, Listed ML20211E1701999-07-28028 July 1999 Forwards Copy of Final Exercise Rept for 990427-29,full- Participation Plume Exposure & Ingestion Pathway Exercise of Offsite Radiological Emergency Response Plans site-specific to VYNPS ML20210G5041999-07-27027 July 1999 Responds to NRC 990301 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions. Licensee Will Submit Info Re Proposed Sys Mod by 990916 ML20210G4271999-07-27027 July 1999 Forwards Testing Data & Associated Results for Fitness for Duty Program at Plant for 990101-0630 ML20210J3031999-07-27027 July 1999 Submits Proposed Changes to Eals.Attachment 1 Provides Listing of Changes to EALs Along with Ref to Bases Documents Supporting Change ML20209J0601999-07-14014 July 1999 Forwards Rev 11 to Vols 1-10 of State of Nh Radiological Emergency Response Plan & Vols 11-50 to Town Radiological Emergency Response Plans,In Support of Vermont Yankee & Seabrook Station.Vols 17-19 of Were Not Included ML20209G1531999-07-12012 July 1999 Discusses Util Setpoint Control Program Implementation Schedule,As Committed to in Licensee 990514 Response to Notice of Violation,Insp Rept 50-271/97-10 ML20196J2321999-06-30030 June 1999 Submits Input from Util Technical Staff Re Soil Disposal on-site Under 10CFR20.2002 & Expresses Interest in Pursuing Approval to Use Same Methodology (Implemented Through Util ODCM & Reported as Noted) If Possible ML20209B6111999-06-29029 June 1999 Resubmits Summary of Vynp Commitments Page to Replace Original Page Submitted with Responding to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20196J7421999-06-29029 June 1999 Informs NRC That Vygs Has Implemented Severe Accident Management,As Committed to in Licensee to NRC ML20209C3751999-06-28028 June 1999 Forwards non-proprietary Rev 16 to EPIP OP 3524, Emergency Actions to Ensure Initial Accountability & Security Response & Proprietary Rev 12 to EPIP OP 3531, Emergency Call-In Method. Proprietary Encl Withheld ML20209B5861999-06-28028 June 1999 Provides Alternative Y2K Readiness Status Described in Supplement 1 to GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure Rept Encl BVY-99-084, Forwards Proprietary Application & Medical Certificate for Mod of Listed SRO License,For Gj Leclair.Gj Leclair Will Be Trained & Evaluated in Accordance with Util Lsro Training Description.Proprietary Info Withheld,Per 10CFR2.7901999-06-18018 June 1999 Forwards Proprietary Application & Medical Certificate for Mod of Listed SRO License,For Gj Leclair.Gj Leclair Will Be Trained & Evaluated in Accordance with Util Lsro Training Description.Proprietary Info Withheld,Per 10CFR2.790 ML20195H1741999-06-15015 June 1999 Forwards Original & Copy of Request for Approval of Certain Indirect & Direct Transfer of License & Ownership Interests of Montaup Electric Co (Montaup) with Respect to Nuclear Facilities Described as Listed ML20195C5891999-05-27027 May 1999 Forwards Response to NRC 990301 RAI Re GL 96-05 Program at Vermont Yankee Nuclear Power Station ML20195D5341999-05-27027 May 1999 Forwards Description of Vermont Yankees Plans for Insp of & Mods to Certain Reactor Vessel Internals BVY-99-074, Forwards Application & Medical Certificate Required for Renewal of Jd Livingston,License OP-10049,RO License.Medical Certificate Withheld1999-05-26026 May 1999 Forwards Application & Medical Certificate Required for Renewal of Jd Livingston,License OP-10049,RO License.Medical Certificate Withheld ML20195B4081999-05-24024 May 1999 Withdraws Licensee Commitment,Contained in ,To Reinitiate ITS Project Following Completion of FSAR Accuracy Verification Project.Util Will Continue to Modify Current TS with Number of Improvements BVY-99-067, Informs That Bw Metcalf,License SOP-1761-9,has Retired from VYNPS & Will No Longer Require License.Nrc Is Requested to Terminate License1999-05-21021 May 1999 Informs That Bw Metcalf,License SOP-1761-9,has Retired from VYNPS & Will No Longer Require License.Nrc Is Requested to Terminate License ML20196L1801999-05-18018 May 1999 Withdraws Licensee & Attachment,Containing Rev 2 to Vermont Yankee Operational QA Manual, from Further Consideration by Nrc.Summary of Commitments Encl ML20206K3201999-05-0707 May 1999 Forwards Response to RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML20206J2801999-04-30030 April 1999 Forwards 1998 Annual Financial Repts for CT Light & Power Co,Western Ma Electric Co,Public Svc Co of Nh,North Atlantic Energy Corp,Northeast Nuclear Energy Co & North Atlantic Energy Svc Corp,License Holders ML20206D3731999-04-27027 April 1999 Informs NRC of Changes in Recipients of NRC Docketed Correspondence ML20206B1401999-04-23023 April 1999 Forwards Replacement of Section 3(a) of NSHC Determination Provided by Re TS Proposed Change 208,suppl Section 6 ML20205S3381999-04-16016 April 1999 Submits Revised Schedule for Response to NRC 990226 RAI Re 980630 Submittal of IPEEE Rept.Info Will Be Submitted by 991231 ML20205S3891999-04-16016 April 1999 Forwards non-proprietary & Proprietary Revised Page to Holtec Rept HI-981932,supplementing TS Proposed Changed 207 Re Spent Fuel Pool Storage Capacity Expansion ML20205S3031999-04-15015 April 1999 Forwards Revised TS Bases Pages 90,227,164 & 221a,accounting for Change in Reload Analysis from Yaec to GE Methodology, Reflecting Change in Condensation Stability Design Criteria & Accounting for More Conservative Calculation ML20205P9291999-04-14014 April 1999 Requests That Rev to NRC 821029 SER for NUREG-0737,Item II.K.3.24,be Issued to Clarify Util Installed RCIC & HPCI HVAC Configuration,As Discovered During Preparation of DBDs for Sys ML20205P8191999-04-13013 April 1999 Forwards Rev 2 to COLR for Vermont Yankee Cycle 20, Dtd Feb 1999,IAW TS Section 6.7.A.4 ML20205M3191999-04-0707 April 1999 Forwards 1998 Annual Rept of Results of Individual Monitoring, Per 10CFR20.2206(b).Licensee Is Submitting Matl to Only Addressee Specified in 10CFR20.2206(c).Without Encl ML20205K0351999-03-31031 March 1999 Informs That Certain Addl Corrections Warranted for 990121 SER for Amend 163 to License DPR-28 Re Suppression Pool Water Temp.Suggested Corrections Listed ML20205K1821999-03-31031 March 1999 Informs of Modifications That Util Made to CO(2) Fire Suppression Sys,Due to Sen 188 Which Occurred at Ineel on 980728.Compensatory Actions Will Remain in Place Until Modifications Are Complete & Systems Are Returned to Svc ML20206A6951999-03-29029 March 1999 Request Confirmation That No NRC Action or Approval,Required Relative to Proposed Change in Upstream Economic Ownership of New England Power Co,Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee 1999-09-29
[Table view] |
Text
_ _ _ _ - _ _ _ _ _ _
VERMONT YANKEE NUCLEAR POWER CORPORATION l
t ,
..- .- % rerry noad. Drattleboro. VT 05301 7002 ENGINE IN OFFICE N
- 680 MAIN st AL ET BOLTON, MA 01740 (b38) 71H711 September 30,1997 BW 97123 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 I
References:
(a) License No. DPR 28 (Docket No. 50 271)
(b) Letter USNRC to VYNPC, NVY 90153, dated October 2,1996 (c) Letter, USNRC to VYNPC, NVY 96-176, dated November 20,1996 (d) Letter, Carl Terry (Niagara Mohawk) to Brian Sheron (USNRC), dated May 30,1997, *BWR Utility Commitments to the BWRVIP"
Subject:
Vermont Yankee's Plans For the 1998 and 1999 Refueling Outages Regarding ReactorVesselInternals in Reference (b) the NRC requested that Vermont Yankee submit its plans for the next inspection of the Core Shroud at Vermont Yankee Nuclear Power Station at least six months prior to the inspection. Additionally, in Reference (c) the NRC requested that Vermont Yankee submit its plans for reinspection of the Core Spray system piping intemal to the reactor pressure vessel at least three months prior to the next refueling outage. The attachment to this letter describes the inspection and repair activities planned for Vermont Yankee's Spring 1998 and Fall 1999 refueling outages as well as additional information regarding implementation of BWRVIP at Vermont Yankee, We trust that this submittal provides the requested information. However, should you have questions or require additionalinformation, please contact this office.
Sincerely, VERMONT YANKEE NUCLEAR POWER CORPORATION r
E'a1n5' V' Donald A. Reid 1
Senior Vice President, Operations g[3 Attachment c: USNRC Region i Administrator USNRC Project Manager VYNPS USNRC Resident inspector VYNPS 9710070158 970930 N N!!$$$hll PDR ADOCK 05000271 g PDR
. VCOMONT Y ANKOH NUCLH AR POWER COH1'OR ATION United States Nuclear Regulatory Commission l . September 30,1997 l Attachment Page 1 of 6 VERMONT YANKEE'S PLANS FOR THE 1998 AND 1999 REFUELING OUTAGES REGARDING REACTOR VESSEL INTERNALS -
Introduction Vermont Yankee is dedicated to the BWRVIP and to the five specific commitments identified in i' Reference (d), Specifically, Vermont Yankee will:
e continue to provide the financial and technical resources needed to complete the BWRVIP Program Plan; e actively participate in completing the BWRVIP Program Plan; e
implement the BWRVlP products at Vermont Yankee Nuclear Power Station as appropriate considering plant schedule, configuration and needs; e
provide timely notification to the NRC staff if Vermont Yankee does not implement the applicable BWRVIP product and e
i continue to work closely with the NRC staff for the successful and timely conclusion of the BWRVIP Program Plan; Pursuant to these commitments Vermont Yankee's plans for our Spring 1998 and Fall 1999 ,
refueling outage as they relate to the BWRVIP are provided below. This letter addresses all of the current BWRVIP requirements regarding inspection scope and scheduling as they apply to the reactor vesselintemals components at Vermont Yankee, in addition to the work described below, Vermont Yankee will also be performing the normal complement of in vessel visual inspections per ASME Secoon XI, General Electric Service Information Letters (SIL's), etc.
during the 1998 and 1999 refueling outages, Core Shroud Vermont Yankee completed an ultrasonic inspection of its circumferential welds in the Spring of 1995, and as a result of that inspection performed a full circumferential weld repair in the Fall of 1990. That repair consisted of four tie rods, in conjunction with the repair, Vermont Yankee performed ultrasonic and eddy current inspections of the repair design reliant welds during the Fall 1990 outage. The design reliant welds consist of portions of eight vertical welds, six ring segment welds and portions of welds H8 and H9 at the jet pump baffle plate.
No cracking was found in any of these welds, Due to Vermont Yankee's aggressive inspection program, the 1990 vertical and ring segment weld inspections will meet the BWRVIP Guidelines for Reinspection of BWR Core Shrouds (BWRVIP 07) requirements for a complete baseline inspection of repaired shrouds, even as they are now being revised (as a result of Nine Mile Point i vertical weld cracking), Because Vermont Yankee has performed a full baseline inspection of the repair design reliant welds, the BWRVIP reinspection frequency does not require Vermont Yankee to perform an inspection in either the 1998 or 1999 outages, in the Spring of 1998, Vermont Yankee will perform the first cycle inspection of all four tie rods.
The inspection will consist of a visual examination to criteria approved by the repair designer.
VERMONT Y ANKcn NUCLEAR l'OWER CORPOR ATION United States Nuclear Regulatory Commission September 30,1997 Attachment Page 2 of 5 1
There will be specific criteria for component condition and patrt engagement, orientation, configuration and interface.
Shroud Sucoort in the Fall of 1996, Vermont Yankee performed ultrasonic and oddy current inspection of walds 4 H8 and H9. No cracking was found. The BWRVIP Shroud Support inspection and Flaw Evaluation Guldelines are in the course of preparation and have not yet been published; however, the Vermont Yankee Fall 1996 inspection meets the requirements of the current BWRVIP draft guidelines for a baseline examination. The BWRVIP draft guideline 4 reinspection frequency does not require Vermont Yankee to perform a reinspection in either the 1998 or 1999 outages, Core Sorav Ploina In the Fall of 1996, Vermont Yankee performed ultrasonic inspection of 39 core spray piping circumferential welds and visual inspection of five circumferential welds that were not acccssible for the ultrasonic inspection. These 44 welds represent 100% of the accessible core spray piping welds. These inspections met the requirements of the BWRVIP Core Spray l Intemals inspection and Flaw Evaluation Guldelines (BWRVIP.18) for a baseline examination.
Two non pressure boundary mechanical welds, where the core spray piping penetrates the core shroud, were found to have indications of possible intergranular stress corrosion cracking.
The flaw analysis evaluated several possible conditions of the core spray piping, including the limiting case where all four mechanical collar welds were completely failed. The NRC evaluated the analysis and authorized operation through the end of Cycle 19 without l performing weld repairs [ Reference (c)). However, the NRC stipulated that operation of l Vermont Yankee beyond Cycle 19 would depend on the satisfactory evaluation of the reinspection results or by implementing acceptable repairs during the next refueling outage.
The BWRVIP core spray piping reinspection frequency for ultrasonic inspection is two cycles.
The 39 welds that were inspected ultrasonically in 1996 would require reinspection in 1999.
The BWRVIP core spray piping reinspection frequency for visual Inspection is one cycle, Therefore, the five welds that were inspected visually in the Fall of 1996 will be reinspected in the Spring of 1998. In 1998 Vermont Yankee will also visually reinspect the two core spray piping welds that exhibited possible cracking.
As a result of the flaws found in 1996 and because of the core spray piping's susceptible material, Vermont Yankee is planning full replacement of the core spray piping system internal -
to the reactor vessel (excluding the spargers), during our 1999 refueling outage. To that end.
Vermont Yankee will proceed to obtain vessel internals as built dimensions during the 1998 refueling outage, as they relate to a core spray piping replacement. Also in that regard, Vermont Yankee is not anticipating a localized repair of one or both r. racked core spray pipe collar welds in 1998, unless the reinspection warrants such a repair.
n .
VHRMONT YANKQu NucLnAR POwnR CORPOR ATION 1
l United States Nuclear Regulatory Commission I . September 30,1997 l
Attachment Page 3 of 5 l
l Core Sorav Soaroers Through the Fall 1996 refueling outage, Vermont Yankee has been following the requirements of IE Bulletin 8013 for the inspection of core spray spargers, Beginning with the Spring 1998 outage Vermont Yankee intends to follow the guidance of the BWRVIP Core Spray Intemals inspection and Flaw Evaluation Guldelines (BWRVIP 18). Per the BWRVIP definition,
, Vermont Yankee is a geometry tolerant plant with regard to its spargers. Accordingly, Vermont Yankee will perform modified VT 1 inspections of the core spray sparger circumferential welds and VT 3 of the nozzles and brackets in 1998. The reinspection frequency for spargers for geometry tolerant plants is two cycles, as defined by BWRVIP 18.
Too Guide The BWRVIP Top Guide inspection and Flaw Evaluation Guidelines (BWRVIP 26) were published in December of 1996. For Vermont Yankee these guidelines would require a VT 1 inspection of welds in two adjacent aligner assemblies every other cycle and a visual inspection every other cycle of rim weld locations made accessible during normal refueling activities. The need to inspect the top guide hold down assemblies is being evaluated by Vermont Yankee.
The welds in question are virtually inaccessible for visual inspection. Vermont Yankee did a
- best effort" visual examination of two of the aligner assemblies in 1996. This best effort was similar to a VT 3 examination. Ultrasonic inspection of these welds has been investigated and accessibility to some of the welds is improved, however, the majority would still not be accessible, even from alternative surfaces, Additionaliy, there are no vendor tools that currently exist or are in development to provide better access for either ultrasonic or visual inspection. Development of inspection tooling has been determined to be cost prohibitive when compared to installing redundant alignment hardware.
The BWRVIP inspection Committee has not yet provided guidance on the examination of the above top guide components. At this time, Vermont Yankee believes that a BWRVIP acceptable visual inspection of these locations at Vermont Yankee would be impractical to perform due to the limited accessibility, and has elected instead to install top guide wedges to preclude the need for any inspection. For plants with top guide wedges, the only inspection required by BWRVIP 26 is to verify that the wedges are in place, Vermont Yankee intends to install top guide wedges during the Fall 1999 refueling outage.
The Spring 1998 refueling outage will be used to acquire the necessary dimensional Information, Because Vermont Yankee intends to install top guide wedges in 1999, Vermont Yankee does not plan to perform any supplementalinspections of the top guide alignment hardware in 1998, except as in preparation for the 1999 refueling outage, Vermont Yankee completed GE SIL No. 588 inspection recommendations in the Fall 1996 refueling outage and will continue to perform examinations as recommended by GE SIL 554 and do visualinspections of top guide beams as they become accessible during the nurmal course of refueling operations.
M
VCHMONT YANKDn NucLnAR PO Nun CORPon ATioN United States Nuclear Regulatory Commission t
September 30,1997 I Attachment l Page 4 of 5 Core Plate The BWRVIP Core Plate Inspection and Flaw Evaluation Guidelines (BWRVIP 25) were also published in December of 1996. For Vermont Yankee these guidelines require an ultrasonic or visual examination of a critical number of rim hold down bolts. The BWR inspection Committee and EPRI are developing a technique to perform ultrasonic examination of these l bolts, but it is not clear that the technique will be ready for the 1998 outage, or that it will bo l suecassful. Currently, there are no vendors capable of delivering such an ultrasonic inspection
! device. In 1996, Vermont Yankee conducted a visual inspection of the top of the rim hold-l down bolts. No problems or anomafies were observed. BWRVIP 25 requires access to both i
the top and the bottom of the bolts it' visual examination is chosen To inspect the bottom of the bolts, the cameras must ba delivered under the core plate. This would be an extreme hardship for any BWR, requiring removal of in core components and CRD's to provide access.
Because installation of wedges would preclude the need for inspection of the core plate rim l hold down bolts, Vermont Yankee's strategy for the core plate is $1m!!ar to that of the top l guide. Vermont Yankee intends to install core plate wedges during the Fall 1999 refueling outage. Vermont Yankee will use the 1998 outage to prepare for the installation in 1999.
Again, because Vermont Yankee intends to install core plate wedges in 1999, we do not plan to perform any inspection on the core plate in 1998, except as in preparation for the 1999 refueling outage. GE SIL No. 588 inspection recommendations were comp'eted during the Fall '
1996 refueling outage, Jet Pumo Assemblies The BWRVIP Jet Pump Assembly inspection and Evaluation Guidelines are not yet published, but because several plants have detected cracking in jet pump riser circumferential welds, inspection of these components has taken on a greater emphasis. Vermont Yankee has followed the development of the BWRVIP jet pump assembly guidelines and is planning to perform inspectinns in the 1998 or 1999 refueling outage. The inspections will meet those guidelines to the best of Vermont Yankee's ability considering the lateness of the issuance of the guidelines relative to the start of the 1998 outage.
The current BWRVIP draft guidelines require a 50% sample of the high priority weles at the next refueling outage. The high priority welds are essentially all of the circumferential welds in the riser, mixer, diffuser and adaptor pieces. At Vermont Yankee there are approximately 100 of these welds. Because of the time available between the projected issuance of the BWRVIP jet pump assembly guidelines this Fall and the start of the Spring 1998 refueling outage, Vermont Yankee may not be in a position to examine 50% of these welds to a standard that meets BWRVIP requirements, Vermont Yankee is currently out to bid for this work. Based on the nature of the proposals we will decide whether to examine these welds ultrasonically or visually or whether to examine just the riser welds or attempt to include the mixer, diffuser and j
i a .
i . VHRMONT Y ANKIIH NUCl EAR POWi!R CORPOR ATION United States Nuclear Regulatory Commission
( . September 30,1997 I
Attachment Pwge 5 of 5 adaptor welds, as well. These deelslons depend on the final form of the BWRVIP Jet pump assembly guidelines and vendor capabilities.
In accordance with recommendations in NUREG/CR.3052, Vermont Yankee also intends to l perform ultrasonic inspection of the jet pump hold down beams during the 1998 refueling
! outage.
l j Standby Llauld Control System l The BWRVIP Standby Liquid Control System inspection and Flaw Evaluation Guidelines l (BWRVIP 27) were published in April of 1997. Per the guidelines, the nozzle to safe end weld j external to the vesselis the only inspection location (within the scope of the BWRVIP) which is j critical to its function. The guidelines state "A volumetric examination of the nozzle to safe
- end weld should be performed, if accessible, at the next outage when inspection tooling is l available and appropriate pre outage planning can be done." The BWRVIP Inspection l Committee and EPRI are currently working on volumetric NDE techniques for these small 1 diameter dissimilar metal welds, but it is not clear when a technique will be ready.
Strategically, the examination will not be that difficult to perform, because it can be done in the drywell, presumably with a manual technique. Vermont Yankee intends to perform this examination if a technique is developed in time for the 1998 refueling outage, it should be j noted that at Vermont Yankee the standby liquid control system safe end is low carbon (0.010%) stainless steel material, and thus not considered to be susceptible to IGSCC.
Symmary As described above anG demonstrated by previous performance, Vermont Yankee believes in an aggressive and conservative approach to performing reactor vesselinternals inspection and repair / replacement through prompt implementation of the BWRVIP emerging recommendations.
d tb N