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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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VERMO'NT YANKEB NUCl EAR POWER CORPORATION N rerry naad. Brameboro, vT os30 woo 2 ENombb orncr
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) w,umuw lG'ON,n MTo m s. e n April 30,1991 U.S. Nuclear Regulatory Commission Washington, D.C. 205$5 Attention: Document Control
References:
a) License No. DPR 28 (Docket No. 50 271) b) Letter, USNRC to VYNPC, Examination Report No. 50 271/91-01 (OL), dated 3/21/91 c) Letter, USNRC to VYNPC (CAL No. 91007), dated 3/11/91 d) Letter, VYNPC to USNRC (BVY 9125), dated 3/8/91 e) Letter, VYNPC to USNRC (BVY 9127), dated 3/8/91
! f) NUREG 0654, dated November 1980
Attachment:
" Root Cause Analysis Summary"
Dear Sir:
Subject:
Corrective Actions Related to Unsatisfactory Performance of I
Licensed Operator Requallfication Program Durin0 the week of February 25, 1991 the NRC conducted lleensed l oaerator roqualification examinations at Vermont Yankee. Based on the results i o those examinations, the Vermont Yankee Licensed Operator Requalification
- (LOR) Program was determined to be unsatisfactory. Vermont Yankee then
- Initiated, per Reference d), a number of corrective actions including an in depth root cause analysis of the unsatisfactory examination results. Those actions were later acknowledged via NRC Confirmatory Action Letter No.91-007 [ Reference c)). This letter provides a confirmation of completion of those actions as well as the- results of our root cause analysis.
Based on the root cause analysis discussed above, it is our determination that the root cause of the unsatisfactory performance of the LOR program was the failure by management to maintain awareness of NRC examination criteria, i
to fully comprehend the increased emphasis placed on command and control
' functions in the conduct of operations, and to translate that emphasis into directives for the operating crews. We have determined that sufficient l Information regarding the NRC criteria existed, tat did not receive an appropriate l level of review and disposition. A more con:prehensive discussion of our l findings and conclusions, as well as a corrective action schedule, are included l In the attached " Root Cause Analysis Summary".
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VERMONT YANKEC NUCLC AR POWER CORPORATION U.S. Nuclear Regulatory Commission April 30,1991 Page 2 in addition to performance of the root cause analysis, Vermont Yankoo committed to development of training for all licensed operators covering lessons learned from the 1991 LOR examination relative to command and control functions and shift supervision communications. We have completed classroom training on these top cs and have also reinforced that training by conducting crow exercises in the simulator for all licensod personnel.
Vermont Yankoo has also further evaluated the dutlos of the on shift and confirmed by Refotonco communicator that were We havo concluded thatdiscussed In Referenco d)dulles should include making the communicator's c)itial in NRC and state notifications and maintaining those commutlications, but should not include data collection responsibilities. The communicator will continue to be an individual who is in addition to those requirod to moet the minimum operating shift com alomont (2 Senior Reactor Operators, 2 Reactor Operators, and the Shift Eng neor) and will be capablo of responding to tho l Control Room within ten m nutes of being summoned during abnormal and emergoney conditions. Non omorgency notifications may be made by members
- of the operating shift complomont. We conclude that this division of dutlos l continues to be responsive to your concerns and is consistent with the guidanco l
contained in Reference f).
We are confident that the actions we have taken to dato, in addition to the further correctivo actions discussed in Attachment a), will significantly improvo our LOR program and will provido a firm basis for recortification of the program.
If you have any questions or require additional information concerning our efforts, please do not hesitato to contact us.
Very truly yours, Vermont Yankee Nuclear Power Corporation
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Warron P. f urphy Senior Vice President,
[.erat ns cc: USNRC Regional Administrator, Roglon i USNRC Recideat inspector, VYNPS USNRC Project Managor, VYNPS
- ROOT CAUSE ANALYSIS
SUMMARY
A. Root Cause The root cause of the unsatisfactory aerformance of the LOR program !
was the fallure of management to mainLain awareness of changes in NRC .
examination criteria, to fully comprehend the increased emphasis placed l on command and control functions in the conduct of operations, and to i translate those concepts into directives for the operating crews.
Finding #1 Inadequate response to available industry Information, including Information Notice No. 90 54 and-various INPO and NUMARC publications.
This Information provides insight into the criteria the NRC is using during requallflcallon examinallons.
Corrective Actions
- 1. Following each industry meeting or workshop attended by the l Training Department Management or Staff a meeting summary will 4 be routed to all appropriate individuals. This summary will include an assessment of the impact the information presented may have on Vermont Yankee. These meeting summaries Will be considered for inclusion on the agenda of the 03erations Curriculum Committee for discussion at the next schedulec meeting. This practice will be implemented by June 1,1991.
- 2. Methods used for disseminating Industry information within the Operations and Training Departments will be reviewed and revised as necessary to assure appropriate and adequate disposition. For example, if the response to this information concludes that "no other action is required", an explanation as to why this is the case should be included. This review and any identifled revisions will be completed by June 1,1991.
- 3. The Operations Curriculum Committee will develop a method for tracking action items to ensure that all Items raised receive adequate attention and response. This item will be included in the agenda of the next meeting and implementation will be accomplished before October 1,1991.
- 4. The - Training Manager will participate. In the Operations Training Instructor meetings. These meetings will be held on a regular basis with an established agenda.
Finding #2 Lack of direction regarding requirements for administration of the LOR Program. Compounding this problem was the use of inexperienced Instructors in the position of LOR program administrator, and the lack of i
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an SRO from the Operations Department dedicated to the requallfication I examination preparation. l Corrective Actions
- 1. The Operations Training Supervisor has overaH responsibility for administration of the LOR program. When assigning day to day I coordination to a subordinate, the assignment should be made to an experienced instructor. This action will be addressed by July l 1, 1991. l
- 2. Training Department Management will develop written duties and responsibilities for the administration of the LOR program. These dulles and responsibilities will be available by July 1,1991.
- 3. The Training Department will develop training on the requirements of the Examiner Standard (NUREG 1021). This training will be 1 provided to all Instructors eligible to teach LOR, the Operations Supervisor, and the Assistant Operations Supervisor. This Training Plan will be ready coincident with the pre exam checklist (as discussed in corrective action 1 under Finding #6) such that !
training can begin on October 1,1991, i
- 4. The Training Department will ensure aggressive resolution of Inspection findings. A <
presented to the Sr. plan Vicefor Implementing President, this action Operations will be by June 1, 1991.
- 5. The Training Department will develop a mechanism to ensure all the requirements of the NUREG, including requirements added by an future revisions are addressed within 60 days of any revision.y
- 6. An Individual training instructor will be assigned the responsibility for LOR exam preparation. This Individual will be an experienced instructor. Also, it is not necessary that the LOR program administrator be the individual responsible for exam preparation. !
I This individual will be designated six (6) months prior to the scheduled exam date.
. - 7. During examination -cycles in which the Operations Training l Suaervisor will be a participant, an experienced Operations Instructor wil be assigned responsibility for LOR issues. This item will be included in the pre exam list, developed by corrective action 1 under Finding #6.
l 8. An SRO from the Operations staff will be designated 60 days prior to the NRC exam. This individual's primary responsibility will be exam support for the Training Department.
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Finding #3 Tralning Management failed to maintain accountability for the LOR Training Program.
Corrective Action
- 1. The Training Manager and Operations Superintendent will review the requirements and objectives of the LOR program. Following this review they will clearly define the responsibilities of the Operations and Training Departments in the LOR Program Description. The Senior Vice President. Operations, will review and approve the LOR Program Description including the description of those responsibilities. The revised LOR Program description will be presented to the Sr. Vice President, Operations by August 1, 1991 for approval.
Finding #4 As the result of the successful 1989 LOR examination, the management of the Training and Operations Departmonts were content with the preparation for the 1991 LOR examination.
Corrective Action
- 1. Annually, Training Department Management, with Operations Department input, will develop a set of formal goals and objec:lvos for the LOR program. It should also be recognized that the need for program change may occur in mid year, based on foodback from industry mootings and/or workshops, and such changes should be anticipated. The goals for the 1992 LOH program will be established by December 1,1991.
Finding #5 There was a lack of specifically assigned dullos and responsibilities for Control Room personnel with a corresponding lack of a standard crew communications policy.
Corrective Actions
- 1. The Operations Department developed a description of the duties and responsibilities of crew personnel following the 1991 exam. A clear and consistent crew communications policy will be developed and added to this document. This document will be reviewed and approved by Senior Management by the beginning of the third LOR cycle scheduled to begin August 6,1991,
- 2. The Operations Training Curriculum Committoo identified a follow item developed at the April 27, 1989 meeting. The recommendations from that meeting regarding the incorporation of 3
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Vermont Yankee management expectations during simulator evaluations in the areas of crew management and communications will be assigned and completed. This will be accomplished by the beginninn of the third LOR cycle scheduled to begin August 6,1911.
- 3. To'further promote improved command and control functions and to -
enhance crew communic'ations, the spare Shift Supervisor will Be required to observe and comment on simulator scenarios at least once per year during LOR training. The Senior Reactor Operator, Control Room Operator and Shift Engineer will be encouraged to observe simulator training scenarios. This practice will be implemented during the second LOR cycle scheduled to begin June 11,1991.
Finding #6.
Fallure to establish a dialogue with other plants that have recently been examined by the NRC prior to the NRC LOR examination at Vermont Yankee.
Corrective Actions
- 1. The Training Department will develop a pre ex6m chocklist for use in preparing for NRC exams to ensure all required items are accompilshed in a timely manner. This checklist will include the requirement to call some recently examined plants, including plants that may have recently been determined unsatisfactory, if possible.
To ensure the checklists remain current, the list will be reviewed periodically. This review will- also be conducted following each revision of NUREG 1021. This checklist will be available by October 1,1991.
- 2. Training Department Management will consider sending Operations Training Instructors to visit other plants in the region to observe simulator training and review results of NRC administered LOR exams at other plants.
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B. Additional Crew Problems it was also determined that another factor contributed to the problems the crews experienced during the NRC LOR exams.
Finding #1 .
Insufficient training in the use of the latest revision of the Emergency Operating Procedures (EOPs).
Corrective Action
- 1. Annually, Training Department Management, with Operations Department input, will develop a set of formal goals and objectives for the LOR program. These goals will ensure an appropriate amount of time is devoted to EOP training. The adequacy of EOP training will be evaluated on a continuous basis, considering crew and instructor input.
- 2. Since EOP tralning forms the core of operators emergency response capabilities, their com alete understanding of these procedures is critical. To facilitate tils understanding, Operations will publish a revised basis document and incorporate it into licensed operator training concurrent with the approved revision to the EOPs.
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C. Secondary Causal Factors Some factors regarding the Interfaco betwoon the Vermont Yankoo staff and the NRC cxamination team may have contributod to the overall problem and definitely lod to some discord betwoon the Vermont Yankoo exam team and the .
NRC oxam team. l Finding #1 l
Poor quality examination pre aaration material was sont to the NRC for i their use during the preparat on for the exam.
Corrective Action
- 1. The chocklist discussed in the correctivo action number i for Item
! A. 6. should include specific requirements for the content and format i of the reference maiorla!s to be sont to the NRC during examination l pr6paration. The NRC should be contacted prior to each oxam to '
discuss their expectations regarding the content and format of refotonen material. This checklist will be available by October ,
1, 1991.
l l Finding #2 1
l A lack of knowledge regarding the rovisions to the Examiner Standard
! (NUREG 1021) In the area of Individual Simulator Critical Tasks (ISCTs).
Corrective Actions 1
- 1. The Training Department will develop training on the requirements of the Examinor Standard (NUREG 1021). This training will bo l provided to all Instructors eligible to teach LOR, the Operations Supervisor, and the Assistant Operations Supervisor. This training I will be completed by October 1,1991.
- 2. The Operations Training Supervisor and his staff will conduct a l
thorough review of all LOR training and examination material, with
! omphasis on simulator scenarlos, to ensure this matorial moots tho l existing NUREG regulromonts. This review will be completed by October 1,1991.
l l Finding #3 The defensive nature in which tho Vermont Yankee staff responded to tho I
changes the NRC desired during the exam and simulator scenario review I
process.
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Corrective Action
- 1. Tral'ning Department Management will standsrdize the method for interfacing with the NRC. Contact- with the NRC -will be the responsibility of the Operations Training Supervisor, or the designee during exams in which he is a candidate. This method will be established by July 1,1901.
- Finding #4 A-difference existed between Vermont Yankee and the NRC regarding the process for validation of simulator scenarlos. l
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Corrective Action
- 1. The Vermont Yankee simulator scenario validation procedure will be I' aresented to the NRC as part of the 60 day letter Vermont Yankee s required to send to NRC. The Intent of this approach is to seek NRC concurrence-with -our validation process well ;n advance of the .
examination date.
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