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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 YANKEEi NOCI:EAn POwEn ColwauATION
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( w^< }x f )1 November 1,1991 U.S. Nuclear Regulatory Commission Washington, D C. 20555 Attn: Document Control Desk
References:
a) License flo. DPR 28 (Docket No. 50-271) b) Letter, USNRC to VYNPC, inspection Report 9123 (NVY 91170),
dated 9/13/91
Dear Sir:
Subject:
Reply to inspection Report 9123, Notice of Violation and Notlet of Deviation During a routine safety inspection conducted on September 3-6, 1991, a violation of NRC requirements and a deviation frcm a r,ommittrent made to NRC were identified. Our response to these items is provided below.
Reference (b) requested Vermo,it Yankee to respond within 30 days from the date of the letter transmitting the Notice of Violation and Notice of Deviation. Reference (b) was issued on September 13, 1991, but was not received by Vermont Yankee until October 3,1991. Based upon these considerations, permission was obtained through Dr. W. Pasclak to provide the requested response within 30 days from the date of letter recolpt.
Y.!Q M ll9_M 10 CFR 71.5 requires that each licensee who transports or offers for transport licensed material outside the confines of its plant shall comply with the applicable sequirements of the regulations appropriate to the mode of transport of DOT in 49 CFR 170 through 189. 49 CFR 172 203 requires in part it,at the description for a shipment of radioactive material must include the name of each radionuclide in the radioactive material and the activity contained in each package of the shipment.
Contrary to the above, on June 25, 1991, the licensee shipped contaminated eevipment as Radioactive Materlat, to Wyle Laborator - s in Huntsville, Alabama, arvj failed to include iron 55 (Fe 55) as an isotope on the manifest, or to account for its activity on the manifest. Fe 55 represents approximately 50% of the activity present for this type of shipment based upon the licensee's current scaling factors. In addition, the calculations utilized to determine isotopic activity for the gamma emitting isotopes present in this shipment were based upon plant data that was at least three years out of date, and no longer accurately reflected current plant conditions.
This is a Severity Level IV vlotation (Supplement V).
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VEllMON't YANKEL NUCLE Aff POWtit CortPOrt ATION Ue Nuclear Regulatory Commission November 1,1991 Page 2 l
MSEQHEI; The initial error in i listing the Iron 55 (Fe 55) Isotope was due to the rnhnual proces6 i used to generate the shipping papers. The regular computer procoss specifically identifies the i appropriate isotopes, including the weak gamma emitters such as Fe 55 Additionally, this process is kept up to date with the latest scaling factors. The manual process, on the other hand, was poorly defined with only a general leference to the applictule DOT regulations. Due to an Individual weakness in training and experience, the person generating the packago was unable to use the computer process and, instead, used this manual one. This, coupled with an inaccurate review, allowed the manifest to go out without the Fe ST be!ng listed and allowed the use of an out of date list of scaling factors.
A complete review of the shipping papers was performed on September 5,1991.
l Corrected, computer generated manifests were sent to the affected laboratory. A cSreful evaluation of tho materials showed the shipment to be well within the previously established :
- controls so no improper preparation, packaging, marking, labelling, placarding, or communicating )
of ha;rards occurred, nor was any activity limit escoeded. Aditionalty, all appropriate personnel
- in the Radiation Protection Department have been given necess to the cumputer program wnich is normally used for radioactive shipments to er,uure that the corn lJuter generated bhlpping papers are used rather inan the manual procest The shipment procedures will be chang *d to requiru the uso of the computer procetc for all applicable shipmeras and more clearly defino the requiremonta for delnfmlning the activity of all isotopes within a shipment. Additionally, the supervisor who is dosignated as the backup to the Radwaste Assistant will be required to generate a full complement of shipping documents for a shipment, either es a tralning exercise or as an actual shipment, every quarter, lhls will be done under the cognizance of the qualified Radwaste Assistant. Such a requirement should adequately maintain the designated support person's skill und knowledge Finally, the designated ,
revlower of the shipments (Plant Health Physicist) will be required to attend an appropriate training program specifio to radwaste shipp'ng and handling, every two calendar years.
The initial training, procedure changes, and surveillances will bu completed by December 31, 1991..
DEVIATION NRC IE Bulletin 79-19 requires in part that licensee's provido initial training and periodic retraining- in the LMT and NRC regulatory requirements, the waste burial license requirements, and the licensee's Instructions and operation procedures for all personnot involved in the transfer, packaging and transport of radioactive material. The ucenseo committed by letter dated September 26,1979, to p ovide training and periodic retraining covering NRC and DOT requirements, and applicable plant procedure requirements for all emol0yees invcived in the transfer, packaging and transport of radioactive material.
The licensee's Training Department Directive 3, requires in part that ' a Training Curriculum Committeo (TCC) should conveno to affirm the Training Department's i-
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VERMONT YANKCC NUCLEAff POWCff CORPOH ATION l
U.S. Nuclear Regulatory Commission ;
November 1,1991 t
Page 3 selection /desolection of tasks for training, determination of training settings, and s6lection of tasks for entrylevel requitements, initial and/or continuing training. The results of the TCC meeting shall be used to update the appropriato tasicto training material cross-f oforence matrix. The licanseo's Radiation Protection Technician Task Tracking Snoet
- 5g9, for shipping end (oceiving radioactive motorials requires blennial training in the selection of appropriato containers and packages, and triennial training in surveying a shipment, surveying transport vehicles, and supervising the loading of radioactive materials.
Contrary to the above, the licensee had not conducted all the task training specified since June 1988, and did not have scheduled any additional training in these areas for the remainder of 1991. This exceeds the two and three year commitments the licensoo has made in response to NRC IE Bulletin 7919. ,
RESPONSi!
IE Bulletin No. 7919 states in part:
" Provide training and periodic retraining in the DOT and NRC regulatory requirements, the waste burial 4conse requirements, and in your instructions and operating procedures for all personnel involved in the transfer, packaging and transport of radioactive material."
In our response letter dated September 26, 1979, wn stated in part:
' Train lng and periodic retraining covering NRC and DOT requirements, and applicable plant procedure requiremer.to is provided for all employees involved in the transfer, packaging and tratisport of radioactive material. Records of this training are maintained.
,, training and periodic retraining in 1) the waste burlat license requirements, and ?)
minimizing low level waste will be provided as appropriate."
At that time we did not define a specific cycle for ihls training. Past practico was to present it on an on gol g basis as needed.
Inspection 90-08 noted that no radwaste training specific to the commitment made in the l
l 1970 letter was presented to some of our Technicians for three years. Training previous to that timo had been performed for Technicians on an undefined periodic basis, Subsequent to that inspection, wo agreed to consider presenting training covering the appropriate subjects during the 1991 training cycle.
in response to insp6ction 90-08, a Radiation Protaction Department supervisor reviewed t the Rr.dlation Protection Technician Training Program and identified two lesson plans which covered the Bulletin material anr1 commitment subject areas in detall, and submitted the formal requests for this training. lne training was presented to all appropriate- technicians prior to September 1991. The training presented fully covered all of the committed areas, including a review of the applicable plant procedures 11 should also be noted that, biennially the supervisors tasked with the radwaste dulles participato la a full training program conducted off-site by a vendor.
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VERMONT YANKLC NUCLE Alf POWCrt CORPO64 AT40N U.S. Nuclear Rogu!atery Commission November 1,1991 Page 4 Prior to this year the retraining subject areas woro determined at the beginning of a year based on a needs determination performed by the Radiation Protection and Training Departments. This determination was made based on previous findings, weakriesses noted, recommendations made through the formal feedback process, and the training records of the present Technicians. Additionally, consideration was given to the criticality of the tasks. Sinco no radwaste shipments were being made in 1909 and 1990, the waste shipment subjects were not considered important for retraining. No specific definition had been made to proscribe the periodicity of training for any subject.
Though this process worked well in meeting the accrediteo process of training, it did not Osbure that if commitments woro mado for specific periods of retraining, that those commitments would be met. To address this issue, meetings were held earlier this year with the Training Department and Radiation Protection Supervision to define the cycles for all task training. These mootings resulted in the formation of a new task matrix which assigned speelfic retraining cycles for all applicablo Technician tasks. This matrix and the process for development was defined in a recently revised Training Department Directive, TDD 3. Because the matrix is all encompassing, it includes all applicable lesson plans, not just the ones appropriate to the training requirod in our commitment. It should be noted that this matrix is in the developmental stage and is intended to be a beginning point for estabilshing the appropriate periodicity of subjects which require on-going review. At no time was a commitment made to meet the requkements of this matrix prior to its finalization. The matrix is not expected to be completed until January 1992, at which time we expect to begin the defined cycles.
We have concluded that we did not deviate from any specific commitment made to the NRC, however, we concede that our program did require the clarifications and improvements noted above to ensure that all tralnlag commitments are mot.
Very truly yours.
Vermont Yankee Nuclear Power Corporation p.
Warren P. furphy Ah I Senior Vico President, pogions
/dm cc: USNRC Regional Administrator, Region i USNRC Resident inspector, VYNPS USNRC Projcet Manager, VYNPS
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