|
---|
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
.. I VERMONT -YANKEE y NUCLEAR POWER CORPORATION 185 Old Ferry Road, Brattleboro, VT 05301-7002
- l (862) 257-5271 Novemb6r 20,1998 BVY 98-155 l U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555
Subject:
Vermont Yankee Nuclear Power Station I i
License No. DPR-28 (Docket No. 50-271)
Request For Alternative Testing Per 10CFR50.55a(a)(3)(1) l Inservice Testing (IST) Program Pursuant to 10CFR55a(s)(3)(i), Vermont Yankee Nuclear Power Corporation (VY) hereby '
requests approval to perform attemative testing to that speedied by the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, and ASME/ ANSI OM, ' Operation and Maintenance of Nuclear Power Plants." Attachment 1 provides the
. Justification for the altemative testing.
Approval for the use of the attemative testing is requested by April 30,1999 in order to support scheduled testing. Upon approval, these altemative methods will be incorporated into our IST Program Plan.
If you have any questions on this transmittal, please contact Mr. Wayne M. Limberger at (802) 258-4237.
Sincerely, VERMONT KF LEAR POWER CORPORATION Gregdfy dMa * " '
Director o ons 'f Attachment )(
cc: . USNRC Region 1 Administrator USNRC Resident inspector-VYNPS USNRC Project Manager-VYNPS q Vermont Department of Public Service ()h 9811300150 981120 I PDR ADOCK 05000271'
.P. PDR b
BW 98-155 \ Pcgs 2 i
4 ATTACHMENT 1 PROPOSED ALTERNATE TEST METHODS RR-P04, Rev.1 High Pressure Coolant injection Pump Testing RR-P10, Rev. 2 Reactor Core isolation Cooling Pump Testing 1
Verm::nt Ycnkee Nucinr Pawcr St:tian Inservice Testing Program RELIEF REOUEST 1
Number: RR-PO4, Revision 1 (Sheet 1 of 3)
SYSTEM: High Pressure Coolant Injection COMPONENTS:
Pump Number Safety Class Drawing Number Dwg. Coord.
P44-1A 2 G-191169 Sh 2 G-11 .
P44-1 A is the High Pressure Coolant Injection (HPCI) main (high prusure) pump. The main - i pump has the safety function to operate in series with the booster pump, P44-1B, to provide
- 1) adequate core cooling and reactor vessel depressurization following a small break loss of i coolant accident, and 2) reactor pressure control during reactor shutdown and isolation.
EXAM OR TEST CATEGORY:
Vibration Velocity (Vv) - (Specifically, Main Pump Turbine Side Horizontal and Vertical Vibration Points I-3,0-3 and Main Pump Gearbox Side Horizontal Vibration Point I-4)
CODE REOUIREMENT: Part 6 Para. 5.2(d) " Test Procedure"
" Pressure, flow rate, and vibration (displacement or velocity) shall be determined and compared with corresponding reference values. All deviations from the reference values shall be compared with the limits given in Table 3 and corrective action taken as specified in para. 6.1."
REOUEST FOR RELIEF:
Reliefis requested on the basis that the proposed alternatives would provide an acceptable level ofquality and safety.
Previous relief was approved for the HP pump in a format that could be interpreted to apply to all
- HP pump vibration points. This revised relief request, being more conservative, is l specifically for vibration points I-3, 0-3 and I-4. The remaining HP and Booster pump vibration points are evaluated using OM-6 acceptance criteria. The HPCI pump has a notable history regarding analysis and resolution of high vibration issues. During the 1985 through 1987 timeframe, vibration consultants with specialized equipment were utilized to identify phase angles, natural and resonance frequencies, etc. providing a thorough analysis of existing
- conditions. The root cause of the higher vibration levels was determined to be a 2nd order acoustical resonance in the piping connecting the low pressure (LP) and high pressure (HP) pumps, and the presence of a structural resonance at the 2nd order in the horizontal direction on
( the HP pump.
i i
Vermont Ycnkse Nucl=r Power Statica Ins:rvice Testing Program 1
RELIEF REOUEST (continued) ;
i !
Number: RR-P04, Revision 1 (Sheet 2 of 3)
I These resonance conditions are design related and have existed since initial pump installation.
The HPCI Booster pump impeller was modified in 1989, based on the consultant's ,
recommendations to reduce the 2nd order vibration levels; however, the overall peak levels remained higher than the OM-6 Table 3a acceptable range of 0.325 in/second. Vermont Yankee concluded that these high levels did not indicate pump mechanical degradation and do not represent phenomena that could prevent the pump from performing its intended function. The NRC approved IST Program Relief Request RR-PO4 in 1993 which permitted the overall peak vibration acceptable range to be expanded to 0.675 in/sec. At that time, Vermont Yankee additionally committed to evaluate the resonance peaks during each test and assigned limits of 1.05 and 1.3 times the overall peak reference value (Vr).
Regarding the approved relief request commitment to evaluate the resonance peaks, VY conservatively interprets " resonance peaks" to be the largest peak on the spectrum even though resonance only occurs when a natural frequency and forced frequency coincide. VY applies the resonance peak criteria to all peaks on the spectrum, the largest usually being the impeller vane ,
pass frequency. Compliance with the VY-proposed spectral resonance alarm criteria of 1.05 and l 1.3 times the overall peak reference value (Vr) results in a hardship without a compensating ;
increase in the quality and safety of the plant. Specifically, spectral a! arm bands are typically j established to be more restrictive in the areas of bearing degradation and less restrictive in the impeller vane pass frequency region. Assignment of a single conservative spectral alarm limit for any large peak on the entire spectrum places the pump in the alert range when, for example, vane pass frequency varies by a small amount. The commitment to perform full spectrum :
vibration monitoring envelopes a review of all peaks in the spectrum for signs of degradation, ;
including the resonance peaks. The VY commitment to assign a single spectral alarm limit adds little value to the vibration program and unjustifiably causes the pump test frequency to be doubled. Relief is requested to delete the conservative spectral alarm commitment.
Additionally, VY has reviewed the overall peak values and determined that the acceptable range limit can be lowered from 0.675 to 0.575 in/sec. This lower acceptance value is the result of continuing efforts to reduce the vibration levels on this complex system (i.e., turbine, HP pump, gearbox, and booster pump combination).
l Vcrmnnt Yc:kee Nucir:r Pcwsr StItis:2 Inservice Testing Program l
l RELIEF REOUEST(continued)
Nurther: RR-PO4, Revision I (Sheet 3 of 3) i ALTERNATE METHOD:
To allow for practicable vibration monitoring of the HPCI HP pump, alternate vibration acceptance criteria are required specifically for vibration points I-3, 0-3 and I-4. Full spectrum analysis will be performed during each quarterly test and the following criteria will be used:
Test Parameter Acceptable Ranne Alert Range Reauired Action Range Vy s 2.5 Vr > 2.5 Vr to and > 6 Vr but not including 6 Vr or
> 0.575 in/sec. but not > 0.70 in/sec. > 0.70 in/sec.
The remaining HPCI High Pressure and Booster pump vibration points are evaluated using OM-6 acceptance criteria.
USNRC EVALUATION STATUS:
Relief was granted in the September 1993 SER [ Reference (s)] for Relief Request RR-P04, Revision 0.
Reliefis pending approval for Relief Request RR-P04, Revision 1, submitted November 1998.
l t
I
4 Verment Yenkea Nucl=r Pcwcr Strticn Inservica Tcsting Prcgram l
RELIEF REOUEST Number: RR-P10, Revision 2 (Sheet 1 of 4) l SYSTEM: Reactor Core Isolation Cooling COMPONENTS: I Pump Number Safety Class Drawing Number Dwg. Coord.
i P47-1A 2 G-191174 Sh 2 F-08 P47-1 A is the Reactor Core Isolation Cooling (RCIC) pump. This pump is powered by a steam driven turbine and has a safety function to operate to provide makeup water to the reactor vessel i during shutdown and isolation in order to prevent the release of radioactive materials to the j environment as a result of inadequate core cooling. The system is designed to receive steam from the reactor vessel and function without AC power from normal supplies or the emergency diesel generators. The pump is a horizontal, multi-stage, centrifugal, double volute pump having five stages with four vanes on the first stage impeller and five vanes on the remaining four impellers, designed to provide a constant flow of 416 gpm at rated speed. The bearings are anti-friction, rolling element type. The RCIC system at VY is designed and qualified for at least 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of continuous or intermittent operation in support of core cooling following transient or accident events. Other plants using this pump design are Quad Cities, Monticello, and Pilgrim.
EXAM OR TEST CATEGORY:
Vibration Velocity (Vv)- (Pump Outboard Bearing, Vertical Vibration Point 0-4) l CODE REOUIREMENT: Part 6 l 1
! Para. 5.2(d) " Test Procedure"
- " Pressure, flow rate, and vibration (displacement or velocity) shall be determined l and compared with corresponding reference values. All deviations from the j reference values shall be compared with the limits given in Table 3 and corrective
, action taken as specified in para. 6.1."
l REOUEST FOR RELIEF:
l Reliefis requested on the basis that the proposed alternatives would provide an acceptable level of quality and safety.
Note: This relief request (Rev. 0) was previously submitted in 1995 and no_1 authorized for long term implementation. The relief request, at that time, requested a 0.5 in/sec.
acceptance range limit for all RCIC pump vibration points. A 1-year interim approval was granted and VY was requested to perform additional investigation and provide an
- enhancedjustification, l
l Vermont Ycnkea Nuclesr Power Station Inservics Testing Prcgrcm l l
RELIEF REOUEST (continued) l Number: RR-P10, Revision 2 (Sheet 2 of 4)
Note: The interim relief request was never implemented by VY. The relief request was l subsequently deleted (Rev.1) from the IST Program with the issuance of revision 18.
The VY course of action in 1995 was to leave the vibration acceptance criteria unchanged, using the OM-6 limits. This action caused, and continues to cause, frequent entry into the Alert Range, requiring increased frequency testing for vibration point 0-4.
This relief request (Rev. 2) will be, upon NRC approval, reinstated in the IST Program.
l This relief request is specifically for the pump outboard bearing in the vertical direction (VY vibration point 0-4). The pump inboaid bearing horizontal / vertical and the outboard bearing horizontal / axial points are evaluated using OM-6 criteria.
Past testing and analysis performed on the RCIC System by Vermont Yankee and independent vibration consultants in 1988 and 1997 confirms characteristic pump vibration levels in the outboard bearing vertical direction, at the high end of the acceptance range criteria stated in !
l Table 3 of Part 6 of the Code. This testing and analysis meets the intent of Paragraph 4.3 and l footnote 1 of Part 6 of the Code.
l The root causes of the higher vibration levels have been determined to be:
a) Excitement in the outboard bearing support in the vertical direction at or near the fourth and fifth orders (vane pass frequency).
b) The presence of a natural frequency at 320 Hz. (19,200 cycles per minute) in the outboard bearing vertical direction.
In the pump speed range of 4,000 to 4,500 RPM the fourth (267-300 Hz) and fifth (333-375 Hz)
- orders do not coincide with the 320 Hz. natural frequency peak but are influenced by it. In ;
general, the 4th order is more sensitive to resonance as pump speed and the corresponding 4th order vane pass frequency are increased toward the 320 Hz natural frequency. The 5th order is influenced somewhat less as speed is lowered, and the corresponding 5th order vane pass frequency is decreased toward the 320 Hz natural frequency.
1 i The analysis performed by a vibration consultant in 1988 docmnented that the 4th order peak value of 0.511 in/sec. @ 4500 rpm dropped to .177 in/sec. when speed was decreased to 4342 rpm. The recommendation at that time was to reduce the speed for surveillance testing. When the surveillance speed was lowered to approximately 4300 rpm the overall peak vibration level in the outboard vertical direction remained in the area of 0.3 in/sec. A reference value of .316 in/sec. was established with a 0.325 in/sec. acceptable range limit. VY has operated the pump with this small acceptable range margin since 3/2/90.
1 i
l 1 Verm:nt Yenk:n Nucinr Pcwer Stati:n Ins:;rvice Testing Prcgram l
RELIEF REOUEST (continued)
Number: RR-P10, Revision 2 (Sheet 3 of 4)
The analysis performed by the same vibration consultant in 1997 clearly documented the relationship of the natural frequency to the 4th and 5th order vane pass frequencies using improved vibration technology. The excitement in the bearing support was also documented.
The recommendation at that time was again to reduce the speed for surveillance testing if possible. If a speed reduction was not possible then changing the number of 1st stage impeller vanes and modifications to the outboard bearing support were recommended.
With only one vertical direction vibration point exceeding the OM-6 vibration criteria it was !
determined that to pursue 1st stage impeller replacement or to perform the analysis to qualify a l bearing support modification results in a hardship without a compensating increase in quality and safety of the plant. Spectrum analysis of the latest surveillance test data shows that the primary source of the vibration continues to coincide with vane pass frequency of the pump. Vane pass frequency is inherent in all pumps and normally does not present a problem unless it happens to excite resonant frequencies. The vane pass frequencies do not coincide exactly with the natural frequency; therefore, a full resonance condition does not exist. The identified vane pass frequencies are on the periphery of resonance excitement, thereby causing higher than expected vibration in the outboard vertical direction. This condition on the outboard bearing, in one direction, is not of a magnitude that would prevent the RCIC pump from performing its intended !
safety function.
Surveillance testing is currently performed to satisfy both Tech. Spec. and IST requirements using a reference speed of 4300 rpm. Preliminary design basis review information indicates that the speed will need to be increased to test the pump at a higher output to account for instrument uncertainty. Increasing the speed to the expected 4450 to 4500 rpm range produces an overall peak vibration between 0.433 and 0.460 in/sec. as documented in the 1997 consultant report.
The resonance condition is design related and has existed since initial pump installation.
Surveillance test documentation collected over a number of years demonstrates that no appreciable degradation has taken place. On 2/18/90 the outboard bearing was replaced three times in an effort to demonstrate that a degraded bearing condition did not exist.
The pump vendor certified, in a 9/14/98 memo, that the pump could be run at 0.575 in/sec. and would not be expected to exhibit reduced reliability given the intermittent and short duration
(< 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) operation in support of core cooling following transient or accident events.
Communication with the aforementioned plants identified that vibration levels of < 0.2 in/sec are routinely experienced; however, it should be noted that their pump pedestals are approximately l'-3" high while the VY RCIC Pump pedestal is 3'-0" in height. With this understanding, a direct comparison between plants cannot be made since the foundation is dissimilar and natural 4
frequencies are unique for each component and combination of components.
l i
Verm:nt Ycrk::e Nuclear Pcwer Statics Ins rvica Testing Pragram RELIEF REOUEST (continued)
Number: RR-P10, Revision 2 (Sheet 4 of 4)
Although existing vibration levels in the RCIC pump outboard bearing vertical direction are at the high end of standard acceptance criteria, they are acceptable and reflect the unique operating characteristics of the VY RCIC pump. It has been concluded that there are no vibration concerns of a magnitude that would indicate pump degradation or prevent the pump from performing its intended function.
ALTERNATE METHOD:
To allow for practicable vibration monitoring of the RCIC pump, altemate vibration acceptance criteria are required. Full spectrum vibration monitoring will be performed during each quarterly test and the following criteria will be used for RCIC pump vibration point 0-4:
Test Parameter Acceptable Range Alert Range Reauired Action Rance V, s 2.5 Vr > 2.5 Vr to and > 6 Vr but not including 6 Vr or
> 0.575 in/sec. but not > 0.70 in/sec.
> 0.70 in/sec.
USNRC EVALUATION STATUS:
Reliefis pending approval for Relief Request RR-PIO, Revision 2, submitted November 1998. )
i l
1 I
P-i