|
---|
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
_. _ _ _
' ' -V'ERMONT YANKEE NUct ' EAR POWER CORPORATION
. W:, s Ferry Road. Brattieboro. VT 05301 7002 y
N
,g) ,
s
- w
[NGINEERING OFFICE MQ MAIN STHf fi BO L10'4 t/ A O t ?d(?
e' 906,1?)6:311 October 25,1991 1 United States Nuclear Regulatory Commission BVY 9198 1 A'ITN: Decument Control Desk '
Washington, DC 20555
References:
- a. License No. DPR 28 (Docket No. 50-271) b, Letier, USNRC to [ All 1.icensees], NVY 91-83, dated April 29,1991 (Generic Letier 9106).
Subject:
Response to Generic Letter 91-06," Resolution of Generic Letter A 30, l Adequacy of Safety Related DC Power Supplies, Pursuant to 10CFR50.54(f). !
Dear Sir:
In Reference (b), USNRC requested all licensees to provide, pursuant to Section 182 of the Atomic Energy Act of 1954 and 10CFR50.54(f), written responses to the questions in Enclosure 1 within 180 days.
Please find as Enclosure 1 Vermont Yankee's response to Reference (b), signed under oath and affirmation. Should you have any further questions or comments regarding the enclosed
. information, please contact this office.
Very truly yours, VERMONT Y ANKEE NUCLEAR POWER CORIORATION Eh _
ames P. Pelletier cc: USNRC Region I . Administrator USNRC Resident inspector- VYNPS USNRC Project Manager- VYNPS STATE OF VERMONT - -) i WINDHAM COUNTY _
. ' ) ss
)
Qk--)
N' z
- j. .
Then personally appeared before me, James P. Pelletier, who, being duly aworn. did state t V '
President' Engineering of Vermont Yankee Nuclear Power Corporation, that he is duly nuttoriiet . c Se the foregaing document in the name and on the behalf of Vermont Yankee Nuclear Power Co n and that t statementi therein are true to the best of his knowledge and belief. ,
i / ;-
,* /% A
~)
gg7ARY 9 k luvnbOM/f -
Janice IL Bepfnett/ Notary I ti 2 911025 My Commission Expires February 10, it
% (PUBUC .f 9[h03h$ostosooo271 p PD" - g, COWTi mm
,.,,n,.un.-, - , - , , , , nnr,,_,~,._,,+
Enclosure 1 Q1. Name the Unit.
Response
The Unit is Vermcnt Yankee Nuclear Power Corporation.
Q2a. How m$ny independent redundant divisions of Class lE or rafety related de power exist at this unit. (Include any separate Class IE or safety related dc, such as any dc dedicated to the diesel generetors.)
Response
There e.re 'cwo independent trains of safety related DC power at Vert,;ont Yankee.
Division SI consists of 125V DC battery A, its associated bus DC-1 and charger CA-1; and 24V DC battery A, its associated bus A and charger A. The 125V DC battery A serves the major DC loads including control power for the diesel generator while 24V bus A serves certain ECCS instrumentation loads.
Division SII consists of 125V DC battery B, its associated bus DC-2 and charger CB-1; 125V DC battery AS-2 and its associated bus DC-2AS and charger CAS-2; and 24V battery L, its associated bus B and charger B. Loads connected to division SII are similar to those connected to division SI except r. hat the electric switchgear loads are normally connected to battery B and can be alternately connected to Lattery AS-2. The 'A' diesel generator is also connected to the AS-2 battery.
Q2b. How many functional safety-related divisions of de power are necessary to attain safe shutdown of this unit.
Response
The DC supply in divisions SI and S1I can each separately supply de power to the necessary emergency loads to attain safe shutdown of the plant.
Q3. Does the control room at this unit have the following separate, independently annunciated alarms and indications for each division of de power?
- a. Alarms
- 1. Battery disconnect or circuit breaker open?
I
_ 2..m -
. . , , _ u. ...,-n. .:m__, ____m___ _ _ . > _ _.
Responset There is no annunciator to alert operators of a battery disconnect of the 125V DC batteries A and B, the AS-2 batteries and the ECCS 24V DC batteries A and B.
- 2. Battery charger disconnect or circuit breaker open (both input ac and output dc)?
Responset An annunciator in the control room alerts operators when there is a disconnect in the 12SV DC battery A charger supply breaker to the DC-1 bus. There are no other annunciators to alert operators of a battery charger disconnect (both input ac and output de) in division SI.
Similarly, there is an annunciator to warn operators of a disconnect in the 125V DC battery B charger supply breake r to the DC-2 bus. There is an annunciator to alert operators of a disconnect in the output DC breakor of charger CAS-2 of battery AS-2. There are no other annunciators to alert operators of a battery charger djsconnect (both input ac and output dc) in division 911.
Howeve r, proper operation of the chargers of the batteries of divisions SI and SII are ensured by an auxiliary operator verifying that the chargers are on during each shift. (3 shifts per day)
- 3. dc system ground?
tiesponse:
There is no specific alarm that alerts operators of a ground on the respective buses in divisions SI and SII _
of the de system.
However,.DC-1, the 125V DC bus in division SI, has a ground detection indicator'in the control room. The indicators are checked by the operators at the beginning of each shift. Therefore, the longest time the ground will remain undetected will be eight hours.
The operators may be alerted to a possible ground by the Battery Voltage Lo alarm depending on the severity of the ground.- The indicator specifies the actual
. problem. The ECCS 24V DC Bus A Failure alarm-alerts operators in the control room when there is a ground on Bus A of division SI. The operator determines the presence of a bus bus failure alarm. ground locally when responding to the The grounds on the buses in division SII are detected similarly by operators in the control room.
2
-, . - . . . .=. - - - . - - -. _ - .
l l
i
- 4. dc bus undervoltage?
-Response:
A common Battery. Voltage Lo annunc! stor alarms in the control room when the voltage of DC-1 in division SI or DC-2 in division SII drops. T; 9 ECCS 24V DC Bus A failure annunciator in the control room alerts operators when there is a low bus voltage on Bus A of division SI.
The operstor res voltage locally, ponds to this alarm and verifies low f
Operators are warned similarly when there is a low voltage on the buses in division SII.
- 5. de bus overvoltage?
Rehponse:
The 125V DC bus in division SI does not have an alarm to alert operators of a bus overvoltage. The ECCS 24V DC Bus A Failure annunciator in the control room alerts operators when there is an overvoltage on Bus A. The operator responds to this alarm and verifies high voltage locally.
Similarly, the 125V DC bus in division SII does not have an alarm to alert operators of a bus overvoltage.
Similarly, DC-2AS of division SII does not have an alarm to alert operators of a bus overvoltage. The ECCS 24V DC Bus B Failure annunciator in the control room alerts operators when there is an overvoltage on Bus B.
- 6. Battery charger failure?
Response
There are annunciators in the control room that alert operators when there is a battery charger failure for the chargers in division SI.
Similarly there are annunciators for the battery chargers in division SII.
It should be noted that the-annunciators pertaining to the battery chargers of the ECCS 24V DC batteries A, B and AS-2 do not specify failure, but indicate trouble.
3
o .
Also, a standby-battery charger is available to substitute for either A-1 or B-1 normal battery chargers in_the event of normal charger failure or maintenanca. This charger is of.the same capacity as the normal battery chargers. A standby-battery charger is also available to substitute for battery charger AS-2 in the event of normal charger failure or maintenance. This battery charger is of the same capacity as the normal battery charger. A standby battery charger is available to substitute for either battery A or B of the ECCS 24VDC normal battery chargers in the event of normal- charger failure or maintenance. A spare battery charger is being purchased by Vermont Yankee and will be kept in storage in the event that the standby battery charger of the ECCS 24VDC system fails to operate.
- 7. Battery discharge Response: '
There is no specific battery discharge alarm available in the control room. The state of battery char determined by using the other available alarms,ge is local and remote indication, operator rounds and periodic surveillance,
- b. Indications
- 1. Battery _ float charge current?
Response
There is no indication in the control room to inform operators of the float charge currents of the individual batteries in both divisions SI and SII.
However, batteries A-1 and A of division SI have locally mounted ammeters for battery current indication.
Similarly, batteries B-1, B and AS-2 of division SII have locally mounted ammeters for battery float charge current indication.
- 2. Battery circuit output current?
Response
There is no indication in the control room to inform operators of the battery circuit output currents of the individual batteries in both divisions SI and SII.
4
However, batteries A-1 and A of division SI have locally mounted ammeters for battery current indication.
Similarly, batteries B-1, B and AS-2 of division SII have locally mounted ammeters for battery current indication.
- 3. Battery discharge?
Response
There is no battery discharge indication in the control room. However, the state of battery discharge is determined by using the other available alarms, local and remote indication, operator rounds and periodic surveillance.
- 4. Bus voltage?
Responset There is no control room indication for the bus voltage of the 125V DC bus DC-1 of division SI. However, the battery voltage of DC-1 is recorded on the computer and can be obtained in the control room. The ECCS 24V DC Bus A of divisicn SI has control room indication of the bus voltage.
Similarly, there is no control room indication of the bus voltage of the 125V DC bus DC-2 of division SII except for the computer indication of the battery voltage. The ECCS 24V DO Bus B and 125V DC bus DC-2AS have control room indication of the bus voltage.
However, locally mounted voltmeters exist on each of the DC buses corresponding to each division of the DC system, i.e. a locally mounted voltmeter exists for DC-1, DC-2, DC-2AS, ECCS 24V DC buses A and B.
- c. Does the unit have written procedures for response to the above alarms and indications?
Response
Vermont Yankee maintains a written procedure for response to all the annunciators listed in Q3. The combination of alarms, alarm response procedures, plant procedures and operator training programs provides the operators with adeguate steps to respond to the indicators listed in Q3.
5
9 Q4. Does this unit have indication of bypassed and inoperable status of circuit breakers or other devices that can be used to disconnect the battery and battery charger from its de bus and the battery charger from its ac power source during maintenance or testing?
Response
This unit does have an annunciator in the control room that alerts operators when certain of the DC-1 or DC-2 breakers are open. This annunciator provides indication of bypass and inoperable status of the battery charger circuit breakers.
Q5. If the answer to any part of question 3 or 4 is no then provide information justifying the existing design, features of the facility's safety related de systems.
Response
As-stated in the response to Q3 and Q4, Vermont Yankee may not have all the specific alarms or indicators listed in the questions but through alternate indications and alarm or the combination of alarms provided, existing alarm response procedures, plant procedures, operator training programs, the indication and alarms provided are adequate.
Q6. (1) Have.you conducted a review of maintenance and testing activities-to minimize the potential for human error causing more than one de division to be unavailable?
(2) Do plant procedures prohibit maintenance or testing on redundant de divisions at the same time?
Response
(1) Procedures generated at Vermont Yankee are written by professionals familiar with the operation of the plant and safety issues surrounding it end therefore steps to minimize human error are inherently introduced in the text. Vermont Yankee has a Procedures Writer's Guide which is used when writing procedures. Inherent to this document is information that helps the writer tc write a procedure that minimizes human errors. As part of this process, a procedure walkthrough is performed by someone familiar with the task to be performed. In addition, after generation, the procedure has to go through a review cycle where the Operations Department personnel who are familiar with the various plant conditions and violations can flag any potential problems. The procedure also has to be approved by the Plant Operations Review Committee (PORC). PORC has to ensure that all safety issues have been addressed-by the procedure.
6
(2) Plant procedures-do not explicitly prohibit maintenance or testing on redundant de divisions at the same time.
However, prior to performing battery performance and service discharge tests, it is necessary to determine that the plant is in a mode that permits the inoperability-of 'h- unrociated battery. Also prior to any maintenance activity on a battery, has to be granted by the Shift Supervisor.The perm [ssion Shift Supervisor is familiar with the status of the plant and the various pieces of equipment that can be rendered inoperable at a given time.
Q7. Are maintenance, surveillance and test procedures regarding station batteries conducted routinely at this plant?
Specifically:
- a. At least once per 7 days are the R 11owing verified to be within acceptable limits:
- 1. Pilot cell electrolyte level?
Response: Yes
- 2. Specific gravity or charging current?
Response Yes
- 3. Float voltage?
Response: Yes
- 4. Total bus voltage on float charge?
Response: Yes
- 5. Physical condition of all cells?
Response: Yes
- b. At least once per 92 days, or within 7 days after a battery discharge, overcharge, or if the pilot cell readings are outside the 7-day surveillance requirements are the following verified to be within acceptable limits:
- 1. Electrolyte level of each cell?
Response: Yes
- 2. The average specific gravity of all cells?
Response: Yes 7
5
'E m
- 3. The specific gravity of each cell?
Response: Yes t
- 4. The average electrolyte temperature of a representative number of cells?
Response
Instead of measuring the average electrolyte temperature of a representative number of cell, the temperature of each cell is measured.
- 5. The float voltage of each cell?
Response: Yes
- 6. Visually inspect or measure resistance of terminals and connectors (including the connectors
-at the de bus)?
Response Yes
- c. At least every 18 months are the following verified:
- 1. Low resistance of each connection (by test)?
Response Yes
- 2. Physical condition of the battery?
. Response: Yes
- 3. Battery charger capability to deliver rated ampere outpilt to the de bus?'
Response
Vermont Yankee is currently revising its battery charger test procedure to include meas cing the load current of the battery chargers. The .evised procedure is scheduled for implementation during the next refueling outage.
4.- The capability of the battery to deliver its design duty cycle to the de bus?
Response
Yes, except every 60 months when the capacity of each battery is verified by a performance discharge test.
This test is then performed in lieu of the design duty test.
8
- 5. Each individual cell. voltage is within acceptable limits during the service test?
Response Yes
- d. At least every 60 months, is the capacity of each battery verified by performance of a discharge test?
Response Yes
- e. At least annually, is the battery capacity verified by performance discharge test, if the battery shows signs of degradation or has reached 85% of the expected service life?
Response
Vermont Yankee procedures meet the intent of IEEE 450 for performance discharge testing. For batteries AS-2 and ECCS 24V DC batteries A and B, the performance discharge test will be performed once each cycle (every eighteen months) when the capacity has reached 90%.
For the 125V DC batteries A-1 and B-1, when the battery capacity reaches 90%, plant procedures require that an engineering evaluation is made to determine whether an immediate replacement is necessary or whether the replacement can be delayed to the next refueling outage.
- 08. Does the plant have operational features such that following loss of one safety related dc power supply or bust
- a. Capability is maintained for ensuring continued and adequate. reactor cooling?
'b. Reactor coolant system integrity and isolation capability are maintained?
- c. Operating procedures, instrumentation (including indicators and annunciators), and control functions are
-adequate to initiate-systems as required to maintain adequate core cooling?
Response
The safety related DC distribution system is divided into divisions SI and SII. Each division providing separate and redundant power to the emergency loeds required under postulated design-basis-accident conditions. Therefore, the failure of any one safety related dc power supply will.not jeopardize:
- a. The capability to taaintain continued and adequate reactor-cooling.
9
- b. Reactor coolant system integrity and isolation capability. (Note: As ptrt of its IPE effort Vermont Yan1.co is analyzing the offects of lecing a DC bus.
The analysis will help verify that continued and adequate reactor cooling is maintained and that reactor coolant system integrity and isolation capability is maintained.)
- c. Existing operating procedures, instrumentation and control functions are adequate to initiate systems required to maintain adequate cote cooling following the loss of one safety related de power supply or bus.
6 k
10
- _ _ _ _ _ _ _ _ _ _ _ _ _ _