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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N3901999-10-25025 October 1999 Advises That Info Provided in & Affidavit Re Holtec Position Paper WS-115,rev 1,repts HI-87113, Rev 0,HI-87114,rev 0,HI-87102 Rev 0 & HI-87112,rev 0,marked Proprietary,Will Be Withheld from Public Disclosure ML20217L8591999-10-21021 October 1999 Discusses 990921 Request for Approval to Perform Alternative Testing as Part of Vermont Yankee Nuclear Power Station IST Program.Informs That Submittal Reviewed Against ASME Code Section XI Requirements & Forwards Safety Evaluation ML20217M1181999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20217D9711999-10-13013 October 1999 Responds to Request That Information Titled Addl Info Re Cycle Specific SLMCPR for Vermont Yankee Cycle 21 Be Withheld from Public Disclosure.Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20217F1261999-10-12012 October 1999 Forwards Update to Previously Submitted RELAP5 Analytical Assumptions for App R,Re RAI of 961104 BVY-99-130, Provides Clarification of Method for Determining MSIV Maximum & Minimum Pathway at Vermont Yankee Nuclear Power Station1999-10-0808 October 1999 Provides Clarification of Method for Determining MSIV Maximum & Minimum Pathway at Vermont Yankee Nuclear Power Station ML20217C1501999-10-0707 October 1999 Forwards Insp Rept 50-271/99-11 on 990809-27.No Violations Noted.Insp Focused on Effectiveness of Engineering Functions in Providing for Safe Operation of Plant BVY-99-128, Submits Listed Addl Info in Support of 990414 Request for Clarification to SER Confirming Adequacy of Space Cooling for HPCI & RCIC Sys,Re Item II.K.3.24 of NUREG-0737.Copy of NEDE-24955,encl1999-10-0606 October 1999 Submits Listed Addl Info in Support of 990414 Request for Clarification to SER Confirming Adequacy of Space Cooling for HPCI & RCIC Sys,Re Item II.K.3.24 of NUREG-0737.Copy of NEDE-24955,encl ML20212J7891999-10-0404 October 1999 Informs That Licensee 980804,0628,29 & 990921 Responses to GL 98-01, Y2K Readiness of Computer Sys at NPPs Acceptable.Nrc Consider Subj GL to Be Closed for Plant ML20212J6501999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of VYNPS on 990913. No New Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues & Insp Plan Through Mar 2000 Encl ML20216J3531999-09-29029 September 1999 Responds to NRC Re Violations Noted in Insp Rept 50-271/99-12 on 990628-0811.Corrective Actions:Based on RFO 20 Maint Rule Outage Performance Review,Task Was Generated to Clarify & Enhance SD Monitoring Process BVY-99-122, Notifies of Intention to Reinstate Original Version of App F in FSAR & Correct Docket Re Assumption That Electrical Power Sys Are Designed IAW Requirements of GDC-171999-09-28028 September 1999 Notifies of Intention to Reinstate Original Version of App F in FSAR & Correct Docket Re Assumption That Electrical Power Sys Are Designed IAW Requirements of GDC-17 BVY-99-114, Provides Notification That Licensee Completed Y2K Remediation Efforts Described in Util 990608 Response to NRC GL 98-01,Suppl 11999-09-21021 September 1999 Provides Notification That Licensee Completed Y2K Remediation Efforts Described in Util 990608 Response to NRC GL 98-01,Suppl 1 BVY-99-113, Requests Approval to Perform Alternative Testing to That Specified by ASME Boiler & Pressure Vessel Code,Section XI & Asme/Ansi OM, Operation & Maint of Nuclear Power Plants. Attachment 1 Provides Justification for Alternative Testing1999-09-21021 September 1999 Requests Approval to Perform Alternative Testing to That Specified by ASME Boiler & Pressure Vessel Code,Section XI & Asme/Ansi OM, Operation & Maint of Nuclear Power Plants. Attachment 1 Provides Justification for Alternative Testing BVY-99-116, Informs of Determination That Wh Schulze,License SOP-10528-1,will No Longer Maintain License at Facility. Termination of License Requested1999-09-21021 September 1999 Informs of Determination That Wh Schulze,License SOP-10528-1,will No Longer Maintain License at Facility. Termination of License Requested BVY-99-121, Requests Extension Until 990929 to Respond to Violations Noted in Insp Rept 50-271/99-12,dtd 990819.Licensee Did Not Receive Rept Until 990830 & Addl Time Is Needed to Prepare & Allow for Adequate Review of Violation Response Submittal1999-09-20020 September 1999 Requests Extension Until 990929 to Respond to Violations Noted in Insp Rept 50-271/99-12,dtd 990819.Licensee Did Not Receive Rept Until 990830 & Addl Time Is Needed to Prepare & Allow for Adequate Review of Violation Response Submittal ML20212C1621999-09-17017 September 1999 Forwards Amend 175 to License DPR-28 & Safety Evaluation. Amend Revises TSs to Enhance Limiting Conditions for Operation & Surveillance Requirements Relating to Standby Liquid Control System BVY-99-118, Responds to RAI Concerning GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions1999-09-16016 September 1999 Responds to RAI Concerning GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions BVY-99-115, Forwards non-proprietary & Proprietary Responses to 990714 RAI Re Civil & Mechanical Engineering Considerations for Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355.Proprietary Encls Withheld1999-09-16016 September 1999 Forwards non-proprietary & Proprietary Responses to 990714 RAI Re Civil & Mechanical Engineering Considerations for Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355.Proprietary Encls Withheld ML20216F3171999-09-13013 September 1999 Forwards Insp Rept 50-271/99-06 on 990621-0801.One Violation Identified & Being Treated as Noncited Violation BVY-99-110, Informs of Util Intent to Replace Commitments Made in Licensee & Subsequently Ack in NRC with Containment Insp Criteria Defined in 10CFR50.55a(b)(2)(vi),per Drywell Coating Insp1999-08-31031 August 1999 Informs of Util Intent to Replace Commitments Made in Licensee & Subsequently Ack in NRC with Containment Insp Criteria Defined in 10CFR50.55a(b)(2)(vi),per Drywell Coating Insp BVY-99-111, Informs That Encl TS Bases Page 91 Has Been Revised to Allow Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line Uncorrected Solution & on-line 3D-Monicore Exposure Corrected Solution1999-08-31031 August 1999 Informs That Encl TS Bases Page 91 Has Been Revised to Allow Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line Uncorrected Solution & on-line 3D-Monicore Exposure Corrected Solution ML20211G4791999-08-27027 August 1999 Forwards Notice of Withdrawal of 990420 Amend Request Re TS on Reloading & Unloading Sequence of Fuel in Reactor Core When All Fuel Removed from Core BVY-99-107, Submits Response to NRC RAI Re Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355 Fuel Assemblies1999-08-26026 August 1999 Submits Response to NRC RAI Re Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355 Fuel Assemblies ML20211E8841999-08-25025 August 1999 Requests That Licensee Provide bldg-specific Justification for Use of Method A.1 at Locations Where Amplification Significantly Exceeds 1.5 Limit Above 8 Hz ML20211E1371999-08-20020 August 1999 Forwards from J Bean to H Miller & FEMA Final Exercise Rept for 990427-29 Plume Exposure & Ingestion Pathway Exercise for Vermont Yankee Nuclear Power Station.No Deficiencies Noted.Areas Requiring C/A Identified ML20211H0851999-08-19019 August 1999 Forwards Insp Rept 50-271/99-12 on 990628-0711 & Nov. Violation Re Failure to Monitor Unavailability of Specific Sys,Structures & Components During Refueling Outage Did Not Allow Adequate Assessment of Maint Effectiveness BVY-99-108, Requests That Gv Bogue,Bj Croke,Vs Ferrizzi,Me French, Bk Mcnutt,Jf Meyer & DM Navarro Take BWR Gfes of OL Exam Administered on 991006.DA Daigler & ST Brown Will Have Access to Exams Before Tests Administered1999-08-19019 August 1999 Requests That Gv Bogue,Bj Croke,Vs Ferrizzi,Me French, Bk Mcnutt,Jf Meyer & DM Navarro Take BWR Gfes of OL Exam Administered on 991006.DA Daigler & ST Brown Will Have Access to Exams Before Tests Administered BVY-99-103, Informs That Util Expects to Submit Approx Twenty Licensing Actions in FY00 & FY01,in Response to Administrative Ltr 99-021999-08-18018 August 1999 Informs That Util Expects to Submit Approx Twenty Licensing Actions in FY00 & FY01,in Response to Administrative Ltr 99-02 BVY-99-100, Forwards Revised Floor Response Spectra Diagrams,Originally Sent as Attachment 1 to Licensee to Nrc.Revised Diagrams Have More Legible Scale Markings1999-08-0202 August 1999 Forwards Revised Floor Response Spectra Diagrams,Originally Sent as Attachment 1 to Licensee to Nrc.Revised Diagrams Have More Legible Scale Markings ML20210M5791999-07-30030 July 1999 Responds to NRC 990726 Telcon Re Status of Resolution for USI A-46 Outliers.Written Summary,By Equipment Category, Listed ML20211E1701999-07-28028 July 1999 Forwards Copy of Final Exercise Rept for 990427-29,full- Participation Plume Exposure & Ingestion Pathway Exercise of Offsite Radiological Emergency Response Plans site-specific to VYNPS ML20210G5041999-07-27027 July 1999 Responds to NRC 990301 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions. Licensee Will Submit Info Re Proposed Sys Mod by 990916 ML20210J3031999-07-27027 July 1999 Submits Proposed Changes to Eals.Attachment 1 Provides Listing of Changes to EALs Along with Ref to Bases Documents Supporting Change ML20210G4271999-07-27027 July 1999 Forwards Testing Data & Associated Results for Fitness for Duty Program at Plant for 990101-0630 ML20216D7321999-07-26026 July 1999 Forwards Insp Rept 50-271/99-05 on 990510-0620.Two Viiolations Being Treated as Noncited Violations ML20209G2721999-07-14014 July 1999 Discusses Licensee Response to RAI Re GL 92-01,Rev 1,Suppl Suppl 1, Rv Structural Integrity, for Vermont Yankee Nuclear Power Station ML20209J0601999-07-14014 July 1999 Forwards Rev 11 to Vols 1-10 of State of Nh Radiological Emergency Response Plan & Vols 11-50 to Town Radiological Emergency Response Plans,In Support of Vermont Yankee & Seabrook Station.Vols 17-19 of Were Not Included ML20209G6931999-07-14014 July 1999 Forwards Request for Addl Info Re Spent Fuel Storage Capacity Expansion ML20209G1531999-07-12012 July 1999 Discusses Util Setpoint Control Program Implementation Schedule,As Committed to in Licensee 990514 Response to Notice of Violation,Insp Rept 50-271/97-10 ML20196J2321999-06-30030 June 1999 Submits Input from Util Technical Staff Re Soil Disposal on-site Under 10CFR20.2002 & Expresses Interest in Pursuing Approval to Use Same Methodology (Implemented Through Util ODCM & Reported as Noted) If Possible ML20196J7421999-06-29029 June 1999 Informs NRC That Vygs Has Implemented Severe Accident Management,As Committed to in Licensee to NRC ML20209B6111999-06-29029 June 1999 Resubmits Summary of Vynp Commitments Page to Replace Original Page Submitted with Responding to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20196J2431999-06-29029 June 1999 Informs That Author Received Call from NRR on Dirt Spreading Ltr & Questions Re Cover Ltr Statement Where Util Asks to Be Allowed to Dispose of Future Soil in Same Manner Provided Same Acceptance Criteria Met ML20209C3751999-06-28028 June 1999 Forwards non-proprietary Rev 16 to EPIP OP 3524, Emergency Actions to Ensure Initial Accountability & Security Response & Proprietary Rev 12 to EPIP OP 3531, Emergency Call-In Method. Proprietary Encl Withheld ML20209B5861999-06-28028 June 1999 Provides Alternative Y2K Readiness Status Described in Supplement 1 to GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure Rept Encl ML20196G5241999-06-22022 June 1999 Responds to Re Changes to Vermont Yankee Guard Training & Qualification Plan,Rev 8,Errata A.No NRC Approval Is Required.Encl Will Be Withheld from Public Disclosure Per 10CFR73.21 BVY-99-084, Forwards Proprietary Application & Medical Certificate for Mod of Listed SRO License,For Gj Leclair.Gj Leclair Will Be Trained & Evaluated in Accordance with Util Lsro Training Description.Proprietary Info Withheld,Per 10CFR2.7901999-06-18018 June 1999 Forwards Proprietary Application & Medical Certificate for Mod of Listed SRO License,For Gj Leclair.Gj Leclair Will Be Trained & Evaluated in Accordance with Util Lsro Training Description.Proprietary Info Withheld,Per 10CFR2.790 ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20195H1741999-06-15015 June 1999 Forwards Original & Copy of Request for Approval of Certain Indirect & Direct Transfer of License & Ownership Interests of Montaup Electric Co (Montaup) with Respect to Nuclear Facilities Described as Listed 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217F1261999-10-12012 October 1999 Forwards Update to Previously Submitted RELAP5 Analytical Assumptions for App R,Re RAI of 961104 BVY-99-130, Provides Clarification of Method for Determining MSIV Maximum & Minimum Pathway at Vermont Yankee Nuclear Power Station1999-10-0808 October 1999 Provides Clarification of Method for Determining MSIV Maximum & Minimum Pathway at Vermont Yankee Nuclear Power Station BVY-99-128, Submits Listed Addl Info in Support of 990414 Request for Clarification to SER Confirming Adequacy of Space Cooling for HPCI & RCIC Sys,Re Item II.K.3.24 of NUREG-0737.Copy of NEDE-24955,encl1999-10-0606 October 1999 Submits Listed Addl Info in Support of 990414 Request for Clarification to SER Confirming Adequacy of Space Cooling for HPCI & RCIC Sys,Re Item II.K.3.24 of NUREG-0737.Copy of NEDE-24955,encl ML20216J3531999-09-29029 September 1999 Responds to NRC Re Violations Noted in Insp Rept 50-271/99-12 on 990628-0811.Corrective Actions:Based on RFO 20 Maint Rule Outage Performance Review,Task Was Generated to Clarify & Enhance SD Monitoring Process BVY-99-122, Notifies of Intention to Reinstate Original Version of App F in FSAR & Correct Docket Re Assumption That Electrical Power Sys Are Designed IAW Requirements of GDC-171999-09-28028 September 1999 Notifies of Intention to Reinstate Original Version of App F in FSAR & Correct Docket Re Assumption That Electrical Power Sys Are Designed IAW Requirements of GDC-17 BVY-99-113, Requests Approval to Perform Alternative Testing to That Specified by ASME Boiler & Pressure Vessel Code,Section XI & Asme/Ansi OM, Operation & Maint of Nuclear Power Plants. Attachment 1 Provides Justification for Alternative Testing1999-09-21021 September 1999 Requests Approval to Perform Alternative Testing to That Specified by ASME Boiler & Pressure Vessel Code,Section XI & Asme/Ansi OM, Operation & Maint of Nuclear Power Plants. Attachment 1 Provides Justification for Alternative Testing BVY-99-114, Provides Notification That Licensee Completed Y2K Remediation Efforts Described in Util 990608 Response to NRC GL 98-01,Suppl 11999-09-21021 September 1999 Provides Notification That Licensee Completed Y2K Remediation Efforts Described in Util 990608 Response to NRC GL 98-01,Suppl 1 BVY-99-116, Informs of Determination That Wh Schulze,License SOP-10528-1,will No Longer Maintain License at Facility. Termination of License Requested1999-09-21021 September 1999 Informs of Determination That Wh Schulze,License SOP-10528-1,will No Longer Maintain License at Facility. Termination of License Requested BVY-99-121, Requests Extension Until 990929 to Respond to Violations Noted in Insp Rept 50-271/99-12,dtd 990819.Licensee Did Not Receive Rept Until 990830 & Addl Time Is Needed to Prepare & Allow for Adequate Review of Violation Response Submittal1999-09-20020 September 1999 Requests Extension Until 990929 to Respond to Violations Noted in Insp Rept 50-271/99-12,dtd 990819.Licensee Did Not Receive Rept Until 990830 & Addl Time Is Needed to Prepare & Allow for Adequate Review of Violation Response Submittal BVY-99-115, Forwards non-proprietary & Proprietary Responses to 990714 RAI Re Civil & Mechanical Engineering Considerations for Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355.Proprietary Encls Withheld1999-09-16016 September 1999 Forwards non-proprietary & Proprietary Responses to 990714 RAI Re Civil & Mechanical Engineering Considerations for Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355.Proprietary Encls Withheld BVY-99-118, Responds to RAI Concerning GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions1999-09-16016 September 1999 Responds to RAI Concerning GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions BVY-99-110, Informs of Util Intent to Replace Commitments Made in Licensee & Subsequently Ack in NRC with Containment Insp Criteria Defined in 10CFR50.55a(b)(2)(vi),per Drywell Coating Insp1999-08-31031 August 1999 Informs of Util Intent to Replace Commitments Made in Licensee & Subsequently Ack in NRC with Containment Insp Criteria Defined in 10CFR50.55a(b)(2)(vi),per Drywell Coating Insp BVY-99-111, Informs That Encl TS Bases Page 91 Has Been Revised to Allow Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line Uncorrected Solution & on-line 3D-Monicore Exposure Corrected Solution1999-08-31031 August 1999 Informs That Encl TS Bases Page 91 Has Been Revised to Allow Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line Uncorrected Solution & on-line 3D-Monicore Exposure Corrected Solution BVY-99-107, Submits Response to NRC RAI Re Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355 Fuel Assemblies1999-08-26026 August 1999 Submits Response to NRC RAI Re Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355 Fuel Assemblies BVY-99-108, Requests That Gv Bogue,Bj Croke,Vs Ferrizzi,Me French, Bk Mcnutt,Jf Meyer & DM Navarro Take BWR Gfes of OL Exam Administered on 991006.DA Daigler & ST Brown Will Have Access to Exams Before Tests Administered1999-08-19019 August 1999 Requests That Gv Bogue,Bj Croke,Vs Ferrizzi,Me French, Bk Mcnutt,Jf Meyer & DM Navarro Take BWR Gfes of OL Exam Administered on 991006.DA Daigler & ST Brown Will Have Access to Exams Before Tests Administered BVY-99-103, Informs That Util Expects to Submit Approx Twenty Licensing Actions in FY00 & FY01,in Response to Administrative Ltr 99-021999-08-18018 August 1999 Informs That Util Expects to Submit Approx Twenty Licensing Actions in FY00 & FY01,in Response to Administrative Ltr 99-02 BVY-99-100, Forwards Revised Floor Response Spectra Diagrams,Originally Sent as Attachment 1 to Licensee to Nrc.Revised Diagrams Have More Legible Scale Markings1999-08-0202 August 1999 Forwards Revised Floor Response Spectra Diagrams,Originally Sent as Attachment 1 to Licensee to Nrc.Revised Diagrams Have More Legible Scale Markings ML20210M5791999-07-30030 July 1999 Responds to NRC 990726 Telcon Re Status of Resolution for USI A-46 Outliers.Written Summary,By Equipment Category, Listed ML20211E1701999-07-28028 July 1999 Forwards Copy of Final Exercise Rept for 990427-29,full- Participation Plume Exposure & Ingestion Pathway Exercise of Offsite Radiological Emergency Response Plans site-specific to VYNPS ML20210G5041999-07-27027 July 1999 Responds to NRC 990301 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions. Licensee Will Submit Info Re Proposed Sys Mod by 990916 ML20210G4271999-07-27027 July 1999 Forwards Testing Data & Associated Results for Fitness for Duty Program at Plant for 990101-0630 ML20210J3031999-07-27027 July 1999 Submits Proposed Changes to Eals.Attachment 1 Provides Listing of Changes to EALs Along with Ref to Bases Documents Supporting Change ML20209J0601999-07-14014 July 1999 Forwards Rev 11 to Vols 1-10 of State of Nh Radiological Emergency Response Plan & Vols 11-50 to Town Radiological Emergency Response Plans,In Support of Vermont Yankee & Seabrook Station.Vols 17-19 of Were Not Included ML20209G1531999-07-12012 July 1999 Discusses Util Setpoint Control Program Implementation Schedule,As Committed to in Licensee 990514 Response to Notice of Violation,Insp Rept 50-271/97-10 ML20196J2321999-06-30030 June 1999 Submits Input from Util Technical Staff Re Soil Disposal on-site Under 10CFR20.2002 & Expresses Interest in Pursuing Approval to Use Same Methodology (Implemented Through Util ODCM & Reported as Noted) If Possible ML20209B6111999-06-29029 June 1999 Resubmits Summary of Vynp Commitments Page to Replace Original Page Submitted with Responding to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20196J7421999-06-29029 June 1999 Informs NRC That Vygs Has Implemented Severe Accident Management,As Committed to in Licensee to NRC ML20209C3751999-06-28028 June 1999 Forwards non-proprietary Rev 16 to EPIP OP 3524, Emergency Actions to Ensure Initial Accountability & Security Response & Proprietary Rev 12 to EPIP OP 3531, Emergency Call-In Method. Proprietary Encl Withheld ML20209B5861999-06-28028 June 1999 Provides Alternative Y2K Readiness Status Described in Supplement 1 to GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure Rept Encl BVY-99-084, Forwards Proprietary Application & Medical Certificate for Mod of Listed SRO License,For Gj Leclair.Gj Leclair Will Be Trained & Evaluated in Accordance with Util Lsro Training Description.Proprietary Info Withheld,Per 10CFR2.7901999-06-18018 June 1999 Forwards Proprietary Application & Medical Certificate for Mod of Listed SRO License,For Gj Leclair.Gj Leclair Will Be Trained & Evaluated in Accordance with Util Lsro Training Description.Proprietary Info Withheld,Per 10CFR2.790 ML20195H1741999-06-15015 June 1999 Forwards Original & Copy of Request for Approval of Certain Indirect & Direct Transfer of License & Ownership Interests of Montaup Electric Co (Montaup) with Respect to Nuclear Facilities Described as Listed ML20195C5891999-05-27027 May 1999 Forwards Response to NRC 990301 RAI Re GL 96-05 Program at Vermont Yankee Nuclear Power Station ML20195D5341999-05-27027 May 1999 Forwards Description of Vermont Yankees Plans for Insp of & Mods to Certain Reactor Vessel Internals BVY-99-074, Forwards Application & Medical Certificate Required for Renewal of Jd Livingston,License OP-10049,RO License.Medical Certificate Withheld1999-05-26026 May 1999 Forwards Application & Medical Certificate Required for Renewal of Jd Livingston,License OP-10049,RO License.Medical Certificate Withheld ML20195B4081999-05-24024 May 1999 Withdraws Licensee Commitment,Contained in ,To Reinitiate ITS Project Following Completion of FSAR Accuracy Verification Project.Util Will Continue to Modify Current TS with Number of Improvements BVY-99-067, Informs That Bw Metcalf,License SOP-1761-9,has Retired from VYNPS & Will No Longer Require License.Nrc Is Requested to Terminate License1999-05-21021 May 1999 Informs That Bw Metcalf,License SOP-1761-9,has Retired from VYNPS & Will No Longer Require License.Nrc Is Requested to Terminate License ML20196L1801999-05-18018 May 1999 Withdraws Licensee & Attachment,Containing Rev 2 to Vermont Yankee Operational QA Manual, from Further Consideration by Nrc.Summary of Commitments Encl ML20206K3201999-05-0707 May 1999 Forwards Response to RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML20206J2801999-04-30030 April 1999 Forwards 1998 Annual Financial Repts for CT Light & Power Co,Western Ma Electric Co,Public Svc Co of Nh,North Atlantic Energy Corp,Northeast Nuclear Energy Co & North Atlantic Energy Svc Corp,License Holders ML20206D3731999-04-27027 April 1999 Informs NRC of Changes in Recipients of NRC Docketed Correspondence ML20206B1401999-04-23023 April 1999 Forwards Replacement of Section 3(a) of NSHC Determination Provided by Re TS Proposed Change 208,suppl Section 6 ML20205S3381999-04-16016 April 1999 Submits Revised Schedule for Response to NRC 990226 RAI Re 980630 Submittal of IPEEE Rept.Info Will Be Submitted by 991231 ML20205S3891999-04-16016 April 1999 Forwards non-proprietary & Proprietary Revised Page to Holtec Rept HI-981932,supplementing TS Proposed Changed 207 Re Spent Fuel Pool Storage Capacity Expansion ML20205S3031999-04-15015 April 1999 Forwards Revised TS Bases Pages 90,227,164 & 221a,accounting for Change in Reload Analysis from Yaec to GE Methodology, Reflecting Change in Condensation Stability Design Criteria & Accounting for More Conservative Calculation ML20205P9291999-04-14014 April 1999 Requests That Rev to NRC 821029 SER for NUREG-0737,Item II.K.3.24,be Issued to Clarify Util Installed RCIC & HPCI HVAC Configuration,As Discovered During Preparation of DBDs for Sys ML20205P8191999-04-13013 April 1999 Forwards Rev 2 to COLR for Vermont Yankee Cycle 20, Dtd Feb 1999,IAW TS Section 6.7.A.4 ML20205M3191999-04-0707 April 1999 Forwards 1998 Annual Rept of Results of Individual Monitoring, Per 10CFR20.2206(b).Licensee Is Submitting Matl to Only Addressee Specified in 10CFR20.2206(c).Without Encl ML20205K0351999-03-31031 March 1999 Informs That Certain Addl Corrections Warranted for 990121 SER for Amend 163 to License DPR-28 Re Suppression Pool Water Temp.Suggested Corrections Listed ML20205K1821999-03-31031 March 1999 Informs of Modifications That Util Made to CO(2) Fire Suppression Sys,Due to Sen 188 Which Occurred at Ineel on 980728.Compensatory Actions Will Remain in Place Until Modifications Are Complete & Systems Are Returned to Svc ML20206A6951999-03-29029 March 1999 Request Confirmation That No NRC Action or Approval,Required Relative to Proposed Change in Upstream Economic Ownership of New England Power Co,Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee 1999-09-29
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VERMONT YANKEE NUCL'EAR POWER CORPORATION
.. gh- Ferry Road, Brattleboro, VT 05301-7002
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) ENGINEERING OFFICE 580 MAIN STREET f GOLTON MA 01740 (508)779-6711 August 4,1993 BVY 93-30 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
References:
a) License No. DPR-28 (Docket No. 50-271) b) Generic Letter 84-15, " Proposed Staff Actions to improve and Maintain Diesel Generator Reliability" c) Letter VYNPC to USNRC, FVY 84-126, " Response to Generic Letter 84-15, Diesel Generator Reliability" d) Letter VYNPC to USNRC, BVY 89-49, " Surveillance Testing of ECCS and SLC Equipment, Supplement 2 to Proposed Change No.85" e) Letter VYNPC to USNRC, BVY 92-133, " Submittal of Vermont Yankee Nuclear Power Corporation Third-Interval inservice Testing Program Plan and Safety Evaluation Responses"
Attachment:
Relief Request RR-V03, Rev.1
Subject:
Proposed Change No. 168 to the Vermont Yankee Technical Specifications- Auxiliary Electric Power System Technical Specifications and Associated Revision to the Vermont Yankee Inservice Testing Program
Dear Sir:
Pursuant to 10CFR Part 50.90 of the Commission's Rules and Regulations, Vermont Yankee Nuclear Power Corporation proposes the following modifications to Appendix A of the Operating License [ Reference a)]. Pursuant to 10CFR Part 50.55a of the Commission's Rules and Regulations, Vermont Yankee Nuclear Power Corporation also proposes the following modifications to the Inservice Testing Program [ Reference e)].
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vonmm nsu o wouan Powon coiwo uuos United States Nuclear Regulatory Commission August 4,1993 Page 2 PROPOSED CHANGES Replace pages 173 and 174 of the Vermont Yankee Technical Specifications with the i attached pages 173 and 174. Add new page 173a, also attached.
Replace Relief Request Number RR-V03 of the Vermont Yankee Inservice Testing Program with the attached revised Relief Request.
l This proposed change modifies the monthly periodic testing of the emergency diesel i generators to permit a slow start test in place of the existing requirement to perform a i monthly fast start test. A fast start test shall be performed every six months in lieu of the !
slow start test. Both the monthly and the every sixth month test will require the engine be run at expected maximum emergency loading not to exceed the continuous rating for a minimum period of one hour. A note has also been added allowing all diesel generator starts to be preceded by an engine prelube and warmup procedures.
In addition, some rearrangement and rewording of the Technical Specification requirements is proposed to enhance usability. However. the only substantive change to the requirements of the Technical Specifications is that which is discussed above.
The proposed change also results in a revision to the testing methods for the emergency diesel generator starting air inlet and vent valves. This is further discussed in the attached revision to Relief Request Number RR-V03 of the Vermont Yankee Inservice Testing Program.
REASON FOR CHANGE The proposed change is requested to increase emergency diesel generator (EDG) reliability and availability by reducing the number of fast start tests. Fast starts have been shown by NRC and industry sponsored research to contribute to diesel generator engine wear and failure. The NRC has endorsed the reduction of fast starts in Generic Letter 84-15,
" Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability" [ Reference b)).
Vermont Yankee has already taken the initiative to incorporate many of the recommendations contained in Reference b) in its maintenance and surveillance program.
Reference c) reported that Vermont Yankee has prelubricated the engine prior to required surveillance tests, and has also limited the rate of engine loading in all surveillance tests except for the once per cycle test which requires the simulation of actual loading. Vermont Yankee now performs a slow start test on maintenance and troubleshooting starts that are not performed to demonstrate operability as required by the Technical Specification.
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vuuum vmu m i s i ui row ui conron unis ;
United States Nuclear Regulatory Commission ,
August 4,1993 Page 3 Vermont Yankee has also improved diesel generator reliability and reduced diesel generator engine wear by modifying Technical Specifications [ Reference d)] to eliminate fast ,
start alternate testing of the diesel generator that were required by Technical Specifications when emergency core cooling systems or related subsystems were declared inoperable. This proposed change will further reduce engine wear and increase diesel reliability by permitting the substitution of a slow start for most starts required by Technical Specifications.
By substituting a slow start for the currently required monthly start test, engine wear would be reduced and the engine would still be tested adequately. A " slow start" is considered a start in which the engine is prelubricated, has prewarmed oil and water circulating and reaches speed and load on a prescribed schedule that is selected to minimize stress and wear. The test demonstrates the ability of the diesel generator to start reliably, and to carry the required load. The capabilities of the cooling system and other support systems are also demonstrated.
A fast start test will be performed every six months in lieu of the slow start. During this test the engine will be prelubricated, and will have prewarmed oil and water circulating. A
" fast start" demonstrates the ability to start within the time required in the accident analysis.
1 in addition, both the monthly test and the six month test will require that the engine be loaded to expected maximum emergency loading not to exceed the continuous rating for a minimum period of one hour. Testing at Vermont Yankee has shown operation for a minimum of one hour ensures that proper cooling of the EDG system occurs and that stable conditions are achieved. In addition, testing for a minimum one hour period is consistent with NP.C guidelines [ Reference b)).
Once per operating cycle, the conditions under which the diesel generators are required to start automatically will be simulated. This test will demonstrate that EDGs will ,
start within 13 seconds and accept emergency loads within the specified starting time. i During this test actual automatic start conditions are simulated. Current practice is that the engine is not prelubricated.
SAFETY CONSIDERATIONS
- The revision of the Technical Specification and the Inservice Testing Program permits slow starts for most monthly periodic tests, and to only require fast starts once every six months. This change would bring Vermont Yankee's testing requirements into conformance with the latest NRC guidance [ Reference b)] to reduce fast st .;ts. Fast starts have been demonstrated to be a contributor to engine wear and premature failure. The revised testing wih still demonstrate that the EDGs are ready to perform their safety function and will I
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vamon vmumcoan rowat conmouxnos I
United States Nuclear Regulatory C ,mmission i August 4,1993 Page 4 ,
increase the reliability and availability of the EDGs. In addition, allowing all planned testing l to be preceded by a prelube period and warmup procedures reduces engine wear. -!
Therefore, approval of this proposed change enhances safety of the plant by reducing engine wear and tear; thereby improving the aval, ability and reliability of the EDGs and reducing the l
possibility of introducing test related failures in the diesel generators.
Additionally, changing the duration of the required test to a minimum period of one hour establishes specific criteria to determine test completion. Testing at Vermont Yankee i
~
has shown that operation for a minimum one hour period demonstrates proper cooling of the EDG system. Vermont Yankee procedures for monthly testing currently require a test ;
duration at maximum emergency loading of one hour followed by 7 additional hours of loaded ;
run. ;
SIGNIFICANT HAZARDS CONSIDERATIONS i The standards used to arrive at a determination that a request for amendment involves .
no significant hazards considerations are included in the Commission's regulations,10CFR l 50.92, which state that the operation of the facility in accordance with the proposed amendment would not:
- involve a significant increase in the probability or consequences of an :
accident previously evaluated; or l
- create the possibility of a new or different kind of accident from any accident previously evaluated; or
- ir;volve a significant reduction in a margin of safety. l The following discussion addresses the proposed changes with respect to each of l these three criteria and demonstrates that the proposed changes do not constitute a !
significant hazard consideration: l
- 1) The proposed change does not involve a significant increase in the probability !
or consequences of an accident previously evaluated. The change only affects !
diesel generator periodic testing. T'1e diesel generators are not accident initiators and the method of testing of the diesels cannot initiate an accident !
and therefore will not increase the probability of an accident. This change to the diesel generator testing method does not impact any FSAR safety analysis. !
The proposed surveillance will still provide assurance that the diesel generator :
is available to mitigate the consequences of accidents previously evaluated. l We believe, as Reference b) states, that "an overall improvement in diesel l engine reliability and availability can be gained by performing diesel generator starts for surveillance testing using engine prelube and other manufacturer
vamou vmn .w a un rowen co u ..n mm United States Nuclear Regulatory Commission August 4,1993 Page 5 recommended procedures to reduce engine stress and wear." In addition, the i test duration of one hour is sufficient to demonstrate that during loaded 1 operation proper cooling of the emergency diesel generators occurs. Thus the l consequences of an accident previously evaluated are not increased.
- 2) The change does not create the possibility of a new or different kind of accident '
from any accident previously evaluated. The proposed change will only affect diesel generator periodic testing. The diesel generators are not accident initiators and the method of testing of the diesels cannot initiate an accident.
This change does not relieve the operation of the diesel generator from existing requirements and the diesel generator is still bounded by the assumptions in the accident analysis. The method of testing provides assurance that the diesel generators are available when needed. The proposed change does not involve any changes in Technical Specification setpoints, plant equipment, plant operation, protective functions or design basis of the plant. Therefore, change in the method of starting, load application and test duration during periodic testing would not create a different type of accident than previously evaluated.
- 3) The change does not involve a significant reduction in the margin of safety.
The proposed change is made to increase the reliability and availability of the EDGs thus enhancing the safety of the plant. Assurance that the diesel generators operate within limits determined to be acceptable continues to be provided. We believe, as Reference b) states, that "an overall improvement in diesel engine reliability and availability can be gained by performing diesel generator starts for surveillance testing using engine prelube and other manufacturer recommended proced.ures to reduce engine stress and wear."
In addition, the test duration of one hour is sufficient to demonstrate that during loaded operation proper cooling of the emergency diesel generators occurs.
Thus improvement in diesel generator reliability and availability c as not involve a reduction in the margin of safety.
Based on the above, Vermont Yankee concludes that the proposed change does not constitute a significant hazards consideration as defined in 10CFR50.92(c).
This proposed change has been reviewed by the Plant Operations Review Committee and the Vermont Yankee Nuclear Safety Audit and Review Committee.
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vnmosi ymix Nrur umow ui com oinuos United States Nuclear Regulatory Commission August 4,1993 Page 6 SCHEDULE OF CHANGE The proposed changes will be incorporated into Vermont Yankee Technical Specifications and Inservice Testing Program as soon as practicable following receipt of your approval.
We trust that the information provided above adequately supports our request.
However, should you have any questions in this matter, please do not hesitate to contact us.
Very truly yours, VERMONT YANKEE NU LEAR POWER CORP.
%dce Donald A. Reid Vice President, Operations DAR/gmf ;
Attachments ,
cc: USNRC Region i Administrator USNRC Resident inspector - VYNPS USNRC Project Manager - VYNPS VT Department of Public Service STATE OF VERMONT )
)ss WINDHAM COUNTY )
Then personally appeared before me Donald A. Reid, who, being duly sworn, did state that he is Vice President- operations of Vermont Yankee Nuclear Power Corporation, that he is duly authorized to execute and file the foregoing document in the name and un the behalf of Vermont Yankee Nuclear Power Corporation, and that the statements therein are true to the best of his knowledge and belief.
M E2m M T b/ANa
[/Qp t;he @a M. Fontaine, Notar'y Public ' ~
uy commissio, expires rebruary 10,1995 j
li IJOTARY 01
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Votuosi hw..r Nrcu. An Powrn Coneon vuoN ATTACHMENT I RELIEF REOUEST Number: RR-V03, Revision 1 (Sheet 1 of 3)
SYSTEM: Diesel Generator Starting Air COMPONENTS: i OM Safety Dwg i Valve Number Cat Class Drawing Number Coor i
AS-24-1A B 3 G-191160 Sh 7 B-16 i AS-24-1B B 3 G-191160 Sh 7 B-03 AS-24-2A B 3 G-191160 Sh 7 B-17 l AS-24-2B B 3 G-191160 Sh 7 B-03 AV-24-1A B 3 G-191160 Sh 7 B-17 :
AV-24-1B B 3 G-191160 Sh 7 B-03 These valves are the Emergency Diesel Generator (EDG) starting air inlet and vent valves. They have safety functions, as a set, to provide starting air to the EDG, to prevent EDG and/or piping ,
damage after the EDG starts, and to prevent inadvertent EDG starts.
EXAM OR TEST CATEGORY:
Category B.
CODE REOUIREMENT: Part 10 Para. 4.2.1.1 " Exercising Test Frequency" :
" Active Category A and B valves shall be tested nominally every 3 months, except as provided by paras. 4.2.1.2, 4.2.1.5, and 4.2.1.7."
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vunmsi m,u; Nnuan Powut Conemunos ATTACHMENT I RELIEF REOUEST Number: RR-V03, Revision 1 (Sheet 2 of 3)
CODE REOUIREMENT fcontinued): Part 10 Para. 4.2.1.3 " Valve Obturator Movement" "The necessary valve obturator movement shall be determined by exercising the valve while observing an appropriate indicator, such as indicating lights which signal the required change of obturator position, or by observing other evidence, such as changes in system pressure, flow rate, level, or temperature, which reflect change of obturator position."
REOUEST FOR RELIEF:
Relief is requested on the basis that compliance with the Code requirements is impractical and that the proposed alternatives would provide an acceptable level of quality and safety.
These valves do not have remote position indication. Measuring the stroke time of these valves by observing stem travel would require disassembly of the operator.
Testing of the inlet valves individually would require the lifting of the power leads to the other valve. Since the stroke timing of these valves is performed by the indirect indication of the respective EDG start time, to lift leads each quarter and perform the necessary EDG fast starts to verify each valve's stroke time would be an undue hardship. Because excessive EDG fast starts are a known contributor to decreased EDG reliability and owing to the criticality of the EDGs as part of the ECCS system, the overall impact of testing these valves in accordance with Code requirements would be an overall decrease in plant safety. Furthermore, since the air start system is not totally redundant (e.g. they share common piping, components and initiating logic), testing of these valves individually on a quarterly basis would not increase the quality and safety of the system.
ALTERNATE METHOD:
During EDG slow start testing performed each month, indirect indication that at least one of the two parallel air start inlet valves opens, and the vent valve closes, will be performed by ensuring the EDG starts.
Revision 5-104
venuost nsiar Nrcuan Powrn coiu oinuos ATTACHMENT I RELIEF REOUEST Number: RR-V03, Revision 1 (Sheet 3 of 3)
ALTERNATE METHOD (continued):
l During EDG fast start testing performed every six months, indirect measurement that at least one of the two parallel air start inlet valves opens promptly, and the vent valve closes promptly, will be performed by ensuring the EDG starts within the Technical Specification limit of 13 seconds. Measuring the EDG start time gives indication of possible valve degradation (as a pair) since any significant changes in valve stroke time will be identified by longer than normal EDG start times.
In addition, to further assess the operational readiness of each air start inlet valve, an independent operability test is performed once per operating cycle. This test will be accomplished by alternately lifting the power leads to one of the two air start l valves, and then measuring the EDG fast start time with the remaining valve in operation.
USNRC EVALUATION STATUS:
Revision 5-105