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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
[Table view] |
Text
, _
v w WiVERMONT YANKEE a TNUCLEAR' POWER CORPORATION
, . . Ferry Road, Brattleboro, VT 05301-70o2 ,,,,
ENGlNEERING OFFICE .
k% ~ '
W MAIN STREET -
BOLTON= MA 01740 l608) 7794711 July 10,1932 BW-92-082 W United States Nuclear Regulatory Commission ATTN: Document Control Desk Washir:gton, DC 20555
References:
.(a). License !Jo; DPR 28 (Docket No. 50-271)
(b) Letter, WNPC to USNRC, BW 91 113, dated November 18,1991 (c) : Letter, USNRC to WNPC, NW 92-23, dated February 18,1992
Subject:
, Response to Request for.Additionalinformation and Resubmittal of Request to
' Dispose of Sil0htly Contaminated Sollin Accordance w!!h 10CFR20.302(a)
Dear Sir:
By Reference (b), Vermont Yankee applied under 10CFR20.302(a) for approval of a proposed alternative disposal method of licensed materials by leaving in place radioactively contaminated SEI
.E and fill materia! located under existing plant structures and buildings.
..NRC requestod additional information via Reference (c). Accordingly, p. ease find Vermont
- Yankee's responses to NRC's request of Reference (c). Also, please find attached a revised a . application document incorporating;as appropriate the information given in rerponse to the questions
. in Reference (c). .This application document replaces that submitted by Reference (b) in its entirety.
Should you have additional questions with regard to th!s application, please contact this office.
Very truly yours,-
Vermont Yankee Nuclear Power Corporation W # W Warren P. phy Senior Vice President, O e ons
- Attachment
. cc: USNRC Region i Administrator USNRC Restdent inspector - WNPS lUSNRC Project Manager WNPS 1 fSF'fSS!R 88?fN[ P,DR
'is , , - , . - . . ~. , . . . . - . - . _ - _ . . _ - . . _ . . . . _ _ . . . - - . . . . , - - . , _ - . _ , _ , . . .
7
.o -e RESPONSE TO NRC REOUEST FOR FURTHER INFORMATION ON Vf CHEM SIN 1; 05/15/92
- 1. -Provide addition information (i.e. calculations) to support the assumption
-that 58,500 cu ft of soil may be contaminated.
ANSVER:. This volume as a worst ca'se scenario, was calculated based on the extremely conservative assumption that the entire 150 ft length of pipa failed and a 120' zone of contamination extended from the pipe down 15 feet to bedrock.
In reality, there may only be s.n approximate 120' conical zone of influence extending down about 15 feet from the failed elbow in the pipeline, and contaninating a volume of about, or less than 10,600 f t 3. The larger, more conservative vclue was selected to emphasize the limited extent of the contamination. It is believed, because of uncertainty about the zone of contamination, a conservative estimate of the total activity can best be msde by assuming that the normal laboratory sample volume of 10 liters of reactor coolant water per week was discharged to the sink over an extended period of 10 years,
- and that all of that water leaked from the pipe into the soil under the Chemistry Laboratory floor.
- 2. Clarify the basis for reporting the radionuclide concentration on a " wet" basis instead of a " dry" basis. Provide the concentration on a " dry" basis, if available.
ANSVER: The samplas were analyzed in the "as found" moist condition without oven drying, and thus, were reported as " wet", 61ch is standard environmental laboratory practice for "in-situ" sample reporting (other than sediment sc ries) .
- The labe atory has indicated that the moisture content of these samples would not be' expected to exceed 10-20%, by weight. A change in density of thic magnitude would not significantly affect the resulting radiological impact, given the uncertainties in other assumptions.
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- 3. There is an unt.sually large distance gap between the sample taken at 37.5 inches and the next ons at 85.5 inches compared to the relatively uniform spacing on the other suples. Since the 37.5 inch sample has the highest concentration, it would seem prudent to have taken samples above and below that level to obtain a more detailed profile of the spatial distribution of the contamination.
Provide justification for this gap or provide data on soil boring sample results for depths closer to the 37.5 inch level, and revise the appropriate data tables.
- 5. The. graph titled " BORING FN-1" presents a misleading representation of the distribution on contamination. The x-axis plots the sample depth in a linear manner, which 1 t is not. Additionally, as discussed in question 3, the large gap of missing data between the highest concentration sample and the next sample skews the data representation. Provide a revised graph (including data from question 3) that appropriately reflects actual scale.
ANSWER: The spacing of sanples taken for analysis in boring FN-1 was as consistent as ': ample recovery allowed. Correct sample depths are r.hown on the graph titled " Boring 'MV-1"". Some of the depths of samples presented in Table 1 are off by 1 fr: a corrected copy of this table is attached. This discrepancy resulted from the use of both the top and the bottom of the lab floor as a dat.un for sampling during the course of the boring operation, and the fact that these reference points were established as exactly 1 ft apart. This ditference was recognized and corrected as part of the original analysis of the data, however, the original values were mistakenly included in Table 1. The graph has been re-plotted using " inches" rather than " feet and fractions" as the abscissa.
- 4. Provide the basis for assuming that disposal of 10 liters / week of radioactive material is a conservative value. Provide information on sample analysis and routines to support your answer.
AF%T.R: Vermont 'innkee Technical. Specification 4.6.B.1.a. states "a sample of reactor coolant shall be taken at least every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and annlyzed for 2
i
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radioactive l iodines of I-131 through I-135 during power operation". Section 4.6.B.1.b, states "an isotopic analysis of a reactor coolant sample shall be made at least once per month". Conversation with plant chemistry personnel and review of completed plant chemistry procedures indicates 1 liter samples are collected and _ brought to the laboratory for analysis on a daily basis. The basic assumption is .that these sr.mples were disposed in the laboratory sink, under the assumption the contents was going to the Chemical Drain Tank. One sample per day equates to 7' liters per week. This value was rounded up to 10'11ters per week.
A 100 m'. aliquot of the monthly sample is analyzed for gamcc emitters. A review ,
of several years . .* of data indicated that recent results were somewhat higher than earlier analyses and would represent a conservative basis for determining the total- activity that may have been disposed to the sink over a protracted time period. Therefor the most recent results available were used to estimate the radionuclide concentration of gamma emitters. A sample of rea tor water, taken in the same time frame, was analyzed by the Yankee Atomic Electric Company, Part 61 Laboratory for all radionuclides important to 10CFR61. The results of these analyses provided the basis for the estimate of radionuclide concentratica and distribution.
It is reasonable to assume that the drain leak began as a small corrosion hole in the drain line near the elbow. This allowed small quantities of liquids to
' leak into the soil. As time progressed, the corrosion continued and the leak -
increased in magnitude and an increasing fraction of the material discharged to the drain leaked. It is unlikely that the entire volume of water leaked out of the-pipe. Undoubte Uy a significant percentage of water followed the path of least resistance, down the open pipe.Neither the exact start time, nor magnitude of-leakage is preciaely known, therefore it is conservatively assumed that all of the estimated liquid discharged to the sink for the previous 10 year period resulted-in leakage. It is believed this approach has resultad in a conservative estimation of the total activity that may have been discharged to the sink and the calculated radiological impact represents the upper bound of exposure.
3
- . s.
- 6. Due to methodology errors that -were Cound in the January 1990 draf t of NUREG/CR-5512, use of that methodology is not appropriate. Provide a reanalysis using other available methodology.
ANSWER: Only the on-site intruder drinking water pathway was analyzed using the NUREG/CR-5512 methodology, which is r.aw reanalyzed. A conservative intruder drinking water scenario can be postulated in which a family settles on site 20 years in the future af ter plant closure and digs a shallow well to obtain its drinking water needs. It_ is postulated that the total activity is that presented in the right hand-column of Table 7, i.e. ,10 years of weekly releases followed
- by 20 years of decay, forms the activity source term. It is further assumed that none of the activity has migrated nor has any of the activity been retarded in its movement to an "undsrground pool", which is the source of drinking water.
Using r.he assumption presented in the Final EIS for 10CFR61 (Ref,1) for natural percolation of precipi*ation into a groundwater system, the measured annual precipitation for the site, and assuming a small area of recharge, a conservative value of total dilution water voltene (and hence specific activity) can be postulated for the drinking water scenario. The methodology presented in Regulatory Guide 1.109 can then be app?.ied to calculate the radiological impacts.
l The_averaga precipitation for Vermont Yankee for the period 1981-1990 was 40" per year. Reference 1 documents an annual precipitation rate of 41" and a percolation rate of-2.9", for a NE. site. We have assumed an area of recharge consisting of a circle of 500 f t. radius (7.85E+05 sq. ft.), which represents a small fraction of the plant site upgradient from the Chemistry 1.aboratory. The assumption _is made that a percolation rate of 2,9" per year occurs for the next 20 years. Converting this volume to milliliters, results in an " underground pool" containing 1.075+11 ml. Table A, presents the specific activities of the i radionuclides of concern.
Using the data from Ts.ble A, and the methodology of Reg. Guide 1.109, (Ref.2;
- - - results in a maximum whole body dose of 6.4E-02 mrt 1/yr to an adult and a maximum L organ dose of 1.9E-01 mrem /yr to the infant liver.
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'i Table A*
Radionuclide Activity and Concentration v
Nuclide Total Concentration Activity l pCi/ml pCi
, H-3 ,
2.6E+04 2.4E-07 Mn-54 4'9E 06 4.6E-17 Fe-55 2.6E+00 2.4E-ll Co-60 3.0E+01 2.8E-10 Cs-134 4.8E-02 4.5E-13 Cs-137- 8.7E+01 8.lE-10 Sr-9G 2.0E-01 1.9E-12 1
Activity from previous submf*tal, Table 7, 10 years of releases 'followed by 20 yea:.; of decay.
Appears as. Tabic _8 in the revised analysis An alternate evaluation was made using the RESRAD code (Ref. 3) . Assumptions for input for this program included: 1) a zone of contamination consisting of a cube whose side was ' equal- to the depth to bedrock, 4.7 meters; 2) the activity consisted of that present s,fter ten years of discharges (Table 5, right column) dispersed within a' calculated l'.6E+05 kg of reil; 3) distribution coefficients s
and a hydraulic conductivity value from NUREC/CR-3332 (Ref. 4). At timo equals 20 years, .the total wholebody- dose was calculated to be 4.6E-02 mrem /yr;
^ essentially all from Tritium.
A third calculation was made using the methodology presented in Reference 4.
' This model provides a -relatively simple approach to ground water transport of radionuclides. lactors considered, and values assigned, in this model are presented in the following Table B.
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Table B q ^'l Groundwater Factors Spill source model point source Ground'watar velocity 0.026 meters /dsy Dispersion coefficienta 2 (long), 1 (trans)
Aquifer thickness 1.47 meters Retardation Coefficients Co-60 860 H-3 1 Fe-55 1290 Mn-54 1290 Sr-90 18 y Cs-134, 137 173 Time since spill (years) 20 Relative well lo ation. Highest nuclide concentration (most conservative)
The results are expressed as a radionuclide concentration in the aquifer at. the
. well location. The radionuclide values from Table 5 as noted above, were used
' as-initial values. The methodology of Regulatory Guide 1.109 (Ref.2) was then applied to determine the dose. A result of 3.76E-01 mrem /yr, whole body served L
to bound and confirm the previous two calculations.
It. should be noted that the major contributor to the radiological impact of the on site drinking water pathway is Tritium. The other radionuclides, due to their
. low concentration, and half-life, do not add any significant contribution to dcse calculated 20 years af ter . release. The well location is critical wh.n retardation effects are considered, and unless the well is in close proximity to
- a - postulated plume , no significant exposure is calculated.
For purpose of evaluation, it is assumed the well is located at the maximum concentration for 6
m u.; . . , -.L each nuclidefidentitied. The results of the' dose analysis indicctes that even
=_with'this assumption,.there is no significant dose. Tritium is assumed to have
- the highest' concentration and no retardation, which results in the only .
radionuclide with the most significant radiological impact of any of the nuclides assumed;in the release'.
7.- ' Provide a discussion on' the correlation between the actual sample concentration and the estimated concentrations to demonstrate that using the
-actual-concentrations would'not result in higher doses. Include the data on- '
sampics tak + at the point immediately below where the pipo penetrates the floor, which had a peak Co-60 concentration of 1.1E+05 pCi/kg.
ANSVER: The: original; intent of the' soil boring sample was to determine if the zone of contamination vas_ local.in-nature, and could be readily-quantified, or
-did-ic_' extend down to: bedrock,-in which case, a more detailed evaluation would be. required. : Asithe 'results show, contamination of Co-60 did extend to bedrock.
'The highest - concentration scoop sample was the material directly beneath the floor' and _ adj acent to the pipe. This volume of contamination was approximately, 1 cu.-ft., and it was entirely removed in the sampling process, so the activity
-at that concentration no longer exists.
Due to = an electrical duct directly below the area- of concern, the core boring
= could not be made directly adjacent' to the pipe and was displaced laterally by approximately four feet. The boring represents a vertical profile taken through a' cone of.ccontamination whose true dimensions are not exactly known. It is n
> speculated: that the high concentration of 1131 pC1/kg from the sample taken at '
labout 4 f t . depth represented. the leading edge of ' the - Co-60 activity at that
' location, e
, Ifz. additional data were available it would likely show elevated activity from-that area upward as distance from the pipe decreased, reaching a maximum adjacent o
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- to the pipe at- the floor interface, possibly approaching the values measured in .
theiscoor sample material previously removed. We do not believe the sample data -
are sufficient to form the bases of an estimate of total activity. The lateral extent of tho ' contamination is not-known~and can not be . determined without extensive corings under essential plant ~ structures, llowever the data does
- represent . a. very satisfactory basis for making a conservative estimate of concentration distribution.
Alternatively, an estimate of. total 3ctivity can be made from an~ estimate of total volume of contamination and an avarage concentration of activity. The total volume .under the full 150 foot length of pipe has been previously estimated in the original submittal as 58,000 ft 3. (Assuming a density of 100 lb/ft*, this is equivalent to 2.65E+06 Kg. ) The average Co-60 concentration (from Table 1 of.the original submittal) is 425 pCi/Kg. This results in an estimate of totali activity - of 1.1E+09 pC1, or, 1.1' mC1. Using the same assumptions,. if the contaminated volume: is 10,000 ft3 , the total activity-estimate:is-1.9E-01 mci. The 10 liter per week discharge over a 10 year period results in a total Co-60 activity at the end of 10 years of 4.lE-01 mci (original submittal, Tabic 5). Thus, the estimates of total activity made from estimates
' of contaminated volumes hoend the estimate used in the analysis. It should be pointed out, that the calculated- radiological . impact comes from Tritium, which vas. estimated from the concentration measured.in reactor water, I
- 8. . Provide a legible map of the disposal site with compass direction and scale,
[ that includes local land use (e.g. , buildings , nearby residences, wells, etc. ) .
u L
ANSWER:. The Vermont Yankee FSAR contains site maps. We have included a copy of Figure 2.2.4, Station Plan that shows the information you request. In general the residences ' located on the west of the site on Cov. Hunt road have individual shallow-wells.as potable water' supplies. As mentioned previously, the ground water flov is from-west to east to the Connecticut River, and away from the j.- 8
residences. The Chemistry 1mboratory, the source of the leakage is located in the lower lovel of the " Office Bldg", adjacent to the " Turbine Bldg". The grid scale of the plan is $00'. The main potable water supply for the site is provided by the " West Well", whose location is shown uear the 345 KV switchyard.
- 9. Describe any physical or administrative barriers to prevent present and/or future intrusion into the disposal site (i.e. during building modification, repair of drain line, and decommissioning activities).
ANSWER:. An appropriate note will be placed on the building prints warning of the material beneath the floor and referencing the file number where doewnentation of these activities are kept.
- 10. What controls are in place to prevent the use of the failed drain line?
ANSWER:. The affected drain lines have been capped. The area around the failed pipe has been backfilled with concrete to the original floor line, and is now inaccessible.
- 11. What plans, if any, are being considered to repair or replace the failed I drain line?
ANSWER: As noted in the response to question 10, the original line has been capped and is inaccessible. New piping has been run above the floor to the collection tank. This work has already been completed and is currently in use and is capable of periodic inspection to preclude a repeat of this event.
9
4 References
- 1. NUREG-0945, Vol.1 Final Environmental Impact Statement on 10CFR61 " Licensing
]
Requirements for Land Disposal of Radioactive Waste", U.S. Nuclear Regulatory Commission, November,1982.
- 2. Regulatory Guido 1.109, " Calculation of Annual Dose to Man from Routino Releases of Reactor Fffluents for the Purpose of Evaluation Compliance with 10CFR50, Appendix I", rev.1, October, 1977.
- 3. RESRAD, ver. 4.3, USDOE, " Methodology Description for Compliance with DOE Order 54005, Chap. IV", in press.
- 4. NUREC/CR-3332, " Radiological Assessment", Chapter 4, U.S. Nuclear Regulatory Commission, September, 1983.
l 10
TABLE 1 (Revised)
SOIL BORING SAMPLE RESULTS 'Soring MW-1)
DEPTH BEIDW TOP OF FLDOR Co-60 MN-54 (inches) (PCi/Kg, wet) 25.5 308 5 37.5 383 339 49.5 1131 914 73.5 296 12 l
104.5 351 1 109.5 21 7 133.5 166 <MDA 160.5 90 5
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