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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] Category:STATE/LOCAL GOVERNMENT TO NRC
MONTHYEARML20059A9061990-08-10010 August 1990 Informs That 900724 Notices of Deposition Suspended Indefinitely Until Further Notice.State of VT Unable to Prepare Adequately for Depositions Until Receipt of Interrogatory Responses from Plant.Related Correspondence ML20056A3861990-07-24024 July 1990 Forwards Signed & Conformed Copies of Listed Documents, Including Document Production Requests Propounded by State of VT to Util (Set 3) & 13 Notices of Depositions of Listed Persons at Listed Times.Related Correspondence ML20055J1591990-07-19019 July 1990 Forwards Affidavit of Wk Sherman for Responses to Interrogatories by State of VT to Vermont Yankee Nuclear Power Corp (Set 4),filed 900718,for Filing.W/Certificate of Svc.Related Correspondence ML20055G8981990-07-0909 July 1990 Forwards Stipulation Enlargement Time, for Filing in Vermont Yankee Nuclear Power Station OL Extension ML20055F5511990-06-28028 June 1990 Forwards Page 46 of Motion to Compel Answers to Document Production Requests Filed on 900626 ML20043H1951990-06-14014 June 1990 Forwards Motion to Compel Answers to Interrogatories to State of VT Set 1.W/Certificate of Svc ML20042H0051990-05-0909 May 1990 Requests Withdrawal of NSHC Extending Expiration of License DPR-28 Until 120321,based on ASLB Ruling Admitting Contention VII ML19332F1431989-12-0101 December 1989 Comments on Proposed Change 153,emergency Tech Spec Change Request Re Uninterruptible Power Supply Sys.State Does Not Agree W/Licensee Basis & Justification for Proposed Action. Addl Alternate Testing Required,Should Change Be Granted ML20248F2631989-09-29029 September 1989 Notifies That Dj Mullett No Longer W/State of VT Dept of Public Svc.Future Mailings Should Be Sent to J Volz ML20247B6431989-08-22022 August 1989 Forwards State of VT Petition for Leave to Intervene & Notice of Appearance in Evidentiary Hearing in Response to Notice of Consideration of Issuance of Amend to OL Extending Expiration Date,For Filing ML20245A7091989-06-0707 June 1989 Comments on Proposed Tech Spec Change 147 to License DPR-28 Re ATWS Rule (10CFR50.62).Licensee Should Explain Why Heat Tracing Operability Should Not Be Verified ML20248F7631989-04-0404 April 1989 Advises That All Future Mailings to Commonwealth of Ma Atty General Ofc Should Be Addressed to J Traficonte & Requests Removal of G Dean from Svc List ML20205N2861988-10-28028 October 1988 Forwards State of VT Supplemental Response to Vermont Yankee First Set of Interrogatories & Requests for Production of Documents,Incorporating Portions of Interrogatory 20 Previously Omitted.Related Correspondence ML20155G9501988-10-0505 October 1988 Forwards Attachment a to State of VT Second Set of Interrogatories & Requests for Production of Documents Filed on 880930.Attachment Inadvertently Omitted from Filing.W/ Certificate of Svc.Related Correspondence ML20151Z7091988-08-15015 August 1988 Requests Addl Info Re Potential Improper Disposal of Licensed Matl,Per Listed Questions & Insp Rept 50-271/88-09, Specifically NRC Recommendations Re Disposition of Estimated 13,500 Cubic Ft of Sludge ML20151A7701988-07-15015 July 1988 Forwards Stipulation Re Fuel Amend.Nrc Has No Objection to Util Terms of Stipulation ML20154H3481988-05-19019 May 1988 Requests Update of Mailing List W/Change of Vernon Board of Selectmen from W Zaluzny to Gd Weyman ML20154H8151988-05-19019 May 1988 Forwards Notice of Withdrawal of Petition of State of VT for Leave to Intervene Filed on 880225.Withdrawal Should Not Be Construed as Abandonment or Waiver of Any Issue or Concern State May Raise in Any Other Matter.W/Certificate of Svc ML20150A9781988-02-25025 February 1988 Forwards Atty General Jm Shannon Request for Hearing & Petition to Intervene Re Util Request to Eliminate Certain ECCS & Standby Liquid Control Sys Testing Requirements ML20150A9981988-02-25025 February 1988 Forwards State of VT Petition for Leave to Intervene & Notice of Appearance Re Consideration of Issuance of Amend to OL & Opportunity for Prior Hearing ML20236P8831987-11-0505 November 1987 Forwards Answer of State of VT to Petitions for Review Filed by New England Coalition on Nuclear Pollution & Commonwealth of Ma & Answer of State of VT to Petition for Review Filed by Applicant.W/Certificate of Svc ML20245D1111987-09-21021 September 1987 Expresses Concerns W/Communication Problem Re State of Nh Emergency Mgt Agency Pertaining to Notification of Two Malfunctions of Emergency Response Alarm Sys at Site. Investigation & Written Response Needed ML20215D8061987-06-0909 June 1987 Requests Formal Participation,Pursuant to ASLB 870526 Order, as Interested State Per 10CFR2.715(c) Re Util Spent Fuel Expansion.Entry of Appearance Encl ML20205R5101987-03-30030 March 1987 Forwards Introductory Statement & Contentions of State of VT Re Util 860425 Application for License Amend to Expand Storage Capacity of Spent Fuel Pool,Per State of VT 870129 Petition to Intervene & ASLB 870302 Order ML20210N5181987-01-29029 January 1987 Corp: Consideration of Issuance of Amend to Facility OL & Proposed NSHC Determination & Opportunity for Hearing.* Forwards State of VT Petition to Intervene ML20210H6671986-07-31031 July 1986 Congratulates on Recent Appointment as NRC Chairman.States Must Be Assured That state-of-the-art Safety Measures Used at Nuclear Power Plants,In Light of Recent Chernobyl Accident.Stringent Safety Stds Should Be Adopted ML20210S2501986-07-0101 July 1986 Expresses Appreciation for NRC Cooperation Re State of VT Study of Plant Containment Sys ML20210S2331986-06-25025 June 1986 Requests Response to Two Addl Questions on NRC Evaluation of Plant,Including Explanation of H Denton Statement Re Ability of Mark I Containments to Survive Severe Accident. NRC Response Encl ML20053C9441982-05-19019 May 1982 Expresses Profound Appreciation for Outstanding Effort on Part of Region 1 in Investigating & Analyzing 820424 Emergency Exercise.Cooperation by Region 1 Personnel Greatly Contributed to Fulfilling Duties to Public ML19260D0461980-02-0101 February 1980 Comments on Proposed Rule Change to 10CFR50:state Supports Upgrading NRC Emergency Planning Regulations.Addl Review of State & Local Govt Emergency Response Plans Necessary for Public Health & Safety ML19256E0021979-10-22022 October 1979 Requests NRC Evaluation of Acceptability of Util Plans to Suspend Work on Torus Column Welding Reinforcements.Response Requested by 791026 ML20023A3851978-10-18018 October 1978 Requests References 5 & 7 to Amend 47 Which Provide plant- Specific Data Used in Transient & Accident Analysis 1990-08-10
[Table view] |
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. DOCKETED USHRC STATE OF VERMONT '8t APR -2 P2 :25 DEPARTMENT OF PUBLIC SERVICE 120 ST ATE STREET STATE OFFICE BUILDING g[j[ f "E Ni ~ ' '#
MONTPELIER 05602 [pf ,1 T E L., 4 02 8 2 8-2 011 i r .5 March 30, 1987 Charles Bechhoefer, Esq.
Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Re: NRC Docket No. 50-271 Vermont Yankee Nuclear Power Corp: Consideration of Issuance of Amendment to Facility Operating License and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing
Dear Mr. Chairman and Board Members:
Enclosed please find the Introductory Statement and Contentions of the State of Vermont in this matter.
Ve.rytqulyyours, 1, . 1
- ,o i ./
' !,% } i f, Dkvi J.' Mullett Special' Counsel Vermont Department of Public Service ,
Special Assistant Attorney General DJM/sj l
\
Enclosures cc: Dr. James H. Carpenter John A. Ritsher, Esq.
Atomic Safety and Licensing Board Ann P. Hodgdon, Esq.
Mr. Glenn O. Bricht Richard J. Goddard Ellyn R. Weiss, Esq.
Carol S. Sneider, Esq.
Diana P. Sidebotham j
40 0 h i G I f
, I
\'
D UNITED STATES OF AMERICA i NUCLEAR REGULATORY COMMISSION ,
ATOMIC SAFETY AND LICENSING BOARD Before Administrative Judges !
- Charles Bechhoefer, Chairman Glenn O. Bright Dr. James H. Carpenter ,
In the Matter of ) l'
)
VERMONT YANKEE NUCLEAR POWER ) Docket No. 50-271-OLA !
I POWER CORPORATION )
) !
(Vermont Yankee Nuclear ) (ASLBP No. 87-547-02-LA Power Station) )
)
. INTRODUCTORY STATEMENT AND CONTENTIONS OF THE STATE OF VERMONT !
I. INTRODUCTION On April 25, 1986, Vermont Yankee Nuclear Power Corporation (hereinafter Vermont Yankee) filed an application seeking an amendment to its facility operating license. The proposed amendment, which was originally noticed at 51 FR 22246, seeks expansion of the storage capacity of the spent fuel pool from the current 2000 fuel assemblies to 2870 fuel l assemblies. Due to a procedural defect in the original notice, the filing of the request for amendment was again noticed at 51 FR 47324. The State of Vermont, among others, filed a timely petition to intervene on January 29, 1987. On March 2, 1987, the Atomic Safety and Licensing Board issued an order permitting the State of Vermont to intervene
" subject to the submission. . .of at least one acceptable
t' I'
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contention." (Order of March 2, 1987 at page 3.) The order j further set March 30, 1987, as the deadline for filing said contentions.
i While numerous potential issues were identified by the State of Vermont in the January 29, 1987 petition to intervene, subsequent study and analysis has enabled the .
State to limit its contentions to those set forth herein.
One of the most critical facts underlying these contentions l concerns the lengthy delay in the availability of a long-term disposal repository for spent fuel, Under the terms of section 301 of the Nuclear Waste Policy Act of 1982 (42 U.S.C. S 10221), the Secretary of Energy is charged with the j r I responsibility of preparing a comprehensive report known as I
the Mission Plan, and designed to permit informed decisions to be made in carrying out the terms of the Act. When the t Mission Plan was first submitted to Congress, it set forth a schedule indicating the availability of a long-term disposal repository by 1998. In recent months, however, the Secretary has submitted an amendment to the Mission Plan which, among other things, concedes the DOE's inability to meet the schedule for construction and completion of the first I repository. (See 52 FR 3695.)
II. Preliminary Discussion !
It is against this backdrop that the issues raised l herein must be considered since, given the inability of the federal government to meet its obligations under the Mission
9 :-
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Plan, and the likelihood of further delay- given the enormity. t 4 1 of the task, the request for expansion of the spent ' fuel-storage pool can be viewed as virtually a request for the right to store at the Vernon site an amount of spent fuel which is over 43 percent greater than that which may be stored now, . and over four and one-half times the amount originally envisioned to be kept on site for even a temporary?
! period, all with no assurances that the.high level waste will not ultimately be greater, both in terms of amount and length j of storage. At the time the facility was constructed and
! made operational, and even at the time that the amendment permitting expansion of the facility from 600 to 2,000 units was approved, it was certainly not envisioned by.the State of i
Vermont, nor, we believe, by anyone else .that the facility l would become an open-ended storage repository for high level
., waste. Indeed, the opposite was contemplated. In a 7
i I ,1 stipulation entered into by the parties to the 1977 spent l
, { fuel pool expansion proceedings, the parties stated that ,
4 j
j "[a]ssuming the spent fuel pool of Vermont Yankee Nuclear i j Power Station is filled, assuming further that there existed :
i j no other place for disposal or storage of Vermont Yankee l 4
- i i
- Nuclear Power Station spent fuel, and assuming that it was j I
necessary to reload all or part of the core'to continue i
operation, the only solution would be to shut the reactor f i
( down." _
(Paragraph 7 of stipulation submitted June 21,-1977 l in Docket No. 50-271.) Moreover, the original contemplation of 600 to 2111 units were attempts to fix limits for a .
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i 1
5
e [
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temporary storage site, rather than a long-term, open-ended, j
! permanent type of high-level waste respository. Clearly, the !
parties to the stipulation, like those to most prior !
i proceedings concerning spent fuel pool expansion, I
contemplated the creation of at least one long-term waste repository within the foreseeable future. This was the intent of all,, including federal and state governments.
Yet, this has not happened, and there is nothing resembling ,
reasonable assurance that it will happen before the pool, if expanded as requested, is again full. Analysis of the contentions put forth herein, as well as those to be advanced by other intervenors, cannot be meaningfully undertaken l l
absent recognition of these realities. ;
i Finally, it should be noted that, as pointed out by ;
Ellyn Weiss, counsel for the NECNP, in her letter of March !
- 16, 1987, the Commission staff has not prepared or forwarded the documents it is obligated to prepare with respect to this application. This has severely handicapped Vermont's ability to fully formulate its contentions. Accordingly, the State j
of Vermont would reserve to the fullest extent possible its l right to supplement, update or otherwise amend these contentions. (In the matter of Carolina Power and Licht, 16 NRC 1069 (1982).)
i I
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III. THE PROPOSED AMENDMENT IS NOT OF THE TYPE AS TO WHICH A NO SIGNIFICANT HAZARDS DETERMINATION CAN PROPERLY BE MADE.
A. Analysis Under the Nuclear Waste Policy Act of 1982 l
Following rulemaking proceedings, the Nuclear Regulatory Commission (hereinafter Commission) adopted a series of rules concerning final procedures and standards on no significant hazards considerations. The Commission, adopting the recommendation of the NRC staff in 1986, concluded that a spent fuel pool expansion request may be the subject of a no l significant hazards determination if:
(1) The storage expansion method consists of either i replacing existing racks with a design which allows closer spacing between stored spent fuel assemblies or
, placing additional racks of the original design on the pool floor if space permits:
l (2) The storage expansion method does not involve rod consolidation or double tiering.
(3) The Keff of the pool is maintained less than or equal to 0.95: and (4) No new technology or unproven technology is utilized in either the construction process of the analytical techniques necessary to justify the expansion.
51 FR 7755.
As noted in the New England Coalition on Nuclear
! Pollutions September 19, 1986 supplemental response to the
) Vermont Yankee application, the legislative history of the I
, "Sholly amendment" (41 U.S.C. S 2239) firmly establishes that Congress did not intend that a spent fuel pool expansion request could or should be brought within the no significant
s 6
I hazards exception to the general requirement of a full hearing:
i Mrs. SNOWE. Would the gentleman anticipate this no i significant hazards consideration would not apply to license amendmentes regarding the expansion of a i nuclear reactor's spent fuel storatge capacity of the reracking of spent fuel pools? l Mr. OTTINGER. If the gentlewoman will yield, tha expansion of spent fuel cools and the rerackina to the spent fuel cools are clearly matters which raise sianificant hazards considerations, and thus <
amendments for such purposes coulid not, under j Section 11 (a), be issued prior to the conduct or completion of any requested hearing or without advance notice. (127 Cong. Record H 8146)
(emphasis added) !
l Further legislative history is quoted at pages 7-12 of NECNP's September 19, 1986 filing, and will not be repeated !
l here. Now, in view of the recent admission by the federal t government that it cannot comply with its own plan under the l
Nuclear Waste Protection Act of 1982 (see Introduction, supra), this conclusion is even more compelling for reasons evident from analysis of the evolution of this issue.
After the original application for expansion of Vermont Nuclear spent fuel pool was filed in November of 1976, the Commission staff evaluated the safety and environmental i
effects of the proposed modifications themselves, but did not consider any potential ramifications of the possibility that a long-term storage site would not be available, or that the i
Vermont Yankee site would thereby become a long-term, and in fact indefinite, storage facility for' high-level waste.
1 Notwithstanding this fact, the initial decision of the Atomic Safety and Licensing Board approved the expansion, relying on
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O a prior Commission policy determination which said, in essence, that individual reactor proceedings need not resolve the long-term waste problem. (In the Matter of Vermont Yankee Nuclear Power Corooration, 6 NRC 436, 438 (1977), l l
citing policy statement at 42 FR 34392-93.) The NRC's basis '
for the cited policy statement lay in the belief that i progress of the overall high-level waste management program !
had been satisfactory, and provided a reasonable basis that a ;
f f
j permanent waste storage facility would be available when i needed. CBLt) The Atomic Safety Licensing and Appeal Board i
affirmed, stating that it saw no reason why effect should not be given to the NRC's " reasonable assurance" finding that a long-term storage site would be available when needed. Qui ;
the Matters of Northern States Power Comoany and Vermont !
i Yankee Nuclear Power Corooration, 7 NRC 41, 49-50 (1978).)
The Board further relied on a statement in the 1977 National Energy Plan indicating that actions had been taken "1a ensure that long-term waste storage facilities are availabic by 1985." (Emphasis supplied.) The NRC affirmed the Board's order, and provided no additional comments.
Subsequently, the decision of the Atomic Safety Licensing and Appeal Board was appealed to the U.S. Court of Appeals for the D.C. Circuit. The Court :emanded, finding that the policy declarations relied on by the licensing and appeal boards were not "the product of a -ulemaking record
< devoted expressly to considering the questions" concerning availability of long-term disposal facilitien. (State of
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i 8 i I Minnesota v. United States Nuclear Reaulatorv commission, 602 i
a F.2d 412 (D.C. Cir. 1979) . ) The court further-ruled that l j these questions could be addressed in the context of generic
! i i proceedings. (602 F.2d at 416-17.) .
j In response to the Court of Appeals' decision, the Commission conducted a generic waste disposal confidence ;
proceeding. The final decision in these proceedings was ;
i ,
j published in the Federal Register on August 31, 1984. (49 FR i
34658.) In that decision, the Commission found reasonable '
assurance that (1) safe disposal of high-level waste and j spent fuel in a mined geologic repository is technically 1
j feasible; 2) such a repository would be available by the i r j years 2007-09, and that sufficient long-term repository -
i
] capacity will be available; 3) high-level waste will be safely managed until long-term hig$-level storage is '
i available; 4) if necessary, spent fuel can be safely stored :
I on-site for at least 30 years beyond expiration of a reactor i
,' site's operating license; and 5) reasonable assurance that j safe independent onsite or offsite storage will be made 1
l available if needed. In the responses to comments on the decision, the NRC discussed the implication of the Nuclear l i
i Waste Policy Act of 1982: t i
The Commission has considered the. effect of i enactment of the Nuclear Waste Policy Act of 1982 i and concludes that the Act provides support for i timely resolution of technical uncertainties and i reduces uncertainties in the institutional
! arrangements for the participation of affected !
states and Indian tribes in the siting and ;
development of repositories and in the long-term l
! i
s 9
f management, direction and funding of the repository j program. The bases for the Commission's conclusion are set forth in the decision and will not be ;
- repeated here. The passage of the Act provides
! evidence of a strong national commitment to the ,
, solution of the radioactive waste management +
problem. I
- l The Commission did not propose to rely on the NWPA as the basis for resolving technical uncertainties. Rather, the Commission found that the NWPA provides a framework for facilitating the solution of the remaining technical issues. Title II of the Act authorizes DOE to undertake steps leading to the construction, operation and maintenance of a deep geologic test and evaluation facility and to conduct the necessary research and development as well as to establish a demonstration l program. The schedule set forth in the Act is consistent with the objectivo of assuring repository operation within the time period i discussed in the Waste Confidence decision. The i " Mission Plan" which is required by the Act will ,
provide an effective management tool for assuring !
that the many technical activities are properly i coordinated and the results of research and development projects are available when needed. i 49 FR 34661.
The uncertainties which the NWPA has attempted to resolve have now been raised again by the inability of the l
Federal Department of Energy to meet its own schedule.
While the above does not purport to be an exhaustive ,
1 j history of this issue, it is sufficient to establish what is pertinent here; namely, that prior determinations that spent fuel pool expansion may pose no significant hazards have been made on the assumption that the period of a site storage was l something less than permanent. Indeed, Chairman Palladino, l
in expressing his additional views on the interim rulo permitting a no significant hazards finding, stated that he i
o 10 believed the decision represented the NRC's "best technical judgment at thg time." (48 FR 14872.) Those asstaptions l l
have been undermined by subsequent developments, most notably ,
the proposed amendment to the Mission Plan, which alerts us j to the very real potential that Vermont Yankee may become an f t
open-ended high-level deposit site. The original assurance that a high-level waste facility would be available by 1985, 4 and then by 1998, and now the admission that even this deadline cannot be met, underscores the inability of the federal government 12 ensure that long-term high-level waste deposit facilities will become available prior to the time Vermont Yankee will be required to file for yet a further !
i expansion. Accordingly, the Atomic Safety Licensing and ,
Appeal Board's conclusions are no longer supportable and cannot be relied upon. At the very least, there exist ,
legitimate questions of fact as to 1) the extent to which there are any assurances of the availability of high-level disposal facilities in light of the federal government's inability to meet its own timetables for assurances of such facilities, and 2) the effect of any such diminution on the public health, safety and welfare, given the lack of such assurances. Under these circumstances, a no significant hazards determination, which would effectively deprive the citizens of Ver$ont of their right to be heard on these questions, would be inappropriate, unwise and unfair.
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! B. Additionally, the Issue of whether the Instant-Anolication May Be the Subiect of A No Sionificant Hazards Determination Must Be Analyzed with Resnect to the Terms of The Low-Level Radioactive Waste Policy Act. f l In 1986, the series of statutes known as the Low-Level. !
i-Radioactive Waste Policy Act became law. (42 U.S.C. SS 2021b I
- 2021J.) The Act'makes clear that it is the policy of the l federal government that responsibilities for low-level waste
{
disposal can best be managed on a regional basis. (42 U.S.C.
S 2021(d) . ) To promote this policy, the Act places a series of responsibilities on the individual states or the compact r regions that states may form. Under the terms of the Act, !
i states or compact regions which have not made provisions for' !
the disposal of all low-level waste generated within their boundaries, upon request of a generator,shall "take title to ,
l l the waste, shall be obligated to take possession of the waste, and shall be liable for all damages directly or indirectly incurred by the generator or owner as a consequence of the failure of the state to take possession of the waste as soon after January 1,1993 as the generator or owner notifies the state that the waste is available for ;
shipment." 42 U.S.C. S 2021e (d) (2) (C) . Moreover, generators ;
within a state that does not comply with a timetable for development of low-level waste disposal facilities must pay significant surcharges to any cut-of-state facility which they use, and may ultimately be denied access to out-of-state disposal facilities. 42 U.S.C. 5 2021e (e) (2) .
t
l 12 e ,
i Given the broad responsibilities imposed on the states l l
under this federal law, a right to a full-scale hearing must be accorded to the state in which a facility seeking spent I fuel pool storage expansion is located. Under the terms of l
the Act, it is the state and its people--not the federal l government--who will bear the ultimate financial burden, and l
l the ultimate risk, attendant to the disposal of the low-level waste generated by the facility. Thus, in a very real sense, l the issue of whether a proposed expansion poses a potentially l :
I significant hazard becomes a localized question, not a j federally preempted one. It is the people of Vermont who !.
must ultimately create a storage site, join a regional f f ,
compact, or pay a significant sum to have another state or compact take title to Vermont generated waste. The ability l
of the state to do any of these things successfully is l
directly correlated to the amount of low-level waste generated within the state. If excessive waste is generated
( in Vermont, there exists a significant likelihood that the 1
state will not have sufficient funds to construct an adequate l disposal facility or pay another state to take the waste.
l Moreover, given most of the states' general lack of enthusiasm about becoming radioactive waste disposal sites, !
it may safely be said that a state generating substantial low-level wasto may not be an attractive partner in a regional compact. Given these potential effects on Vermont's j l
l ability to do what it is compelled to do under the federal Act, it cannot be said that the proposed amendment does not
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involve a significant increase in the probability or consequences of an accident previously evaluated (i.e., one !
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resulting from the presence of essentially "nondisposable" i low-level waste), or does not involved a significant reduction in margin of safety to the people of' Vermont. '
Accordingly, a no significant hazards determination.cannot properly be made with respect to this application, and the l State of Vermont should receive a full hearing at which these issues can be thoroughly explored and properly resolved. To do less would be to deny the State of Vermont its fundamental i t
protections and rights. . !
IV. THE APPLICATION FOR EYPANSION OF THE SPENT FUEL POOL :
CANNOT BE GRANTED ABSENT PREPARATION OF AN ENVIROBBIENTAL IMPACT STATEMENT.
Under section 102 of the National Environmental Policy Act of 1969 (42 U.S.C. S 4332), appropriate agencies of'the federal government must prepare an environmental impact statement in connection with any proposed federal action "significantly affecting the quality of the human environment." While it is recognized that this contention has been rejected in earlier cases (e.g., In the Matter of Northern States Power Co. , 6 NRC 265 (1977)), the subsequent i developments with respect to both high and low-level waste storage facilities (see contention III, angra) warrant i re-examination of the issue at this time. An environmental impact statement is required whenever the proposed federal action is major and its effect on the human environment i i
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significant. (Han1v v. Mitchell, 460 F.2d 640, 644 (1972).)
Determinations that spent fuel pool expansion applications have not met this test, and require only an environmental t
impact assessment, do not and cannot govern here, given their often explicit assumption that long-term waste disposal ,
I' facilities would be available in timely fashion. Perhaps the l
best example of this explicit assumption is found in 10 CFR !
S 51.23, wherein the Commission set forth its generic determination that spent fuel storage on site will have no i significant environmental impacts for at least thirty years beyond expiration of reactor operation licenses. The very next sentence of that section states that "the Commission believes there is reasonable assurance that one or more mined i geologic repositories for commercial high-level radioactive waste and spent fuel will be available by the year l 4
i l 2007-2009..." Now that this assumption has been severely ,
undermined, and that no real concrete prospect for long-term storage can be said to exist, the issue must realistically be examined f rom the perspective of whether open-ended storage at the Vernon site constitutes a major federal action significantly affecting the human environment. It has been ,
L
! the federal government's intention to resolve uncertainties and to provide assurances that the issue of disposal would be resolved at a fixed, definite time. Thos established deadlines have consistently been missed from the beginning of the federal government's attempts to establish a site. The DOE's acknowledgment of its inability to meet its own ,
i
a o l l schedule underscores this deficiency. No fixed time period j can be met by the federal government. No assurances have l I
legitimately been provided. No uncertainties have been removed. Given this uncertaintly, the NRC must find that an EIS is necessary.
- 7. EXPANSION OF THE SPENT PUEL POOL MAY EXACERBATE THE EPPECTS OF A SEVERE ACCIDENT.
i If a severe accident were to occur at the Vermont Yankee !
I facility, it is apparent that it is the citizonry of Vermont who would suffer the consequences most severely and most immediately. Because of the serious potential that an expanded number of on-site spent fuel assemblics would exacerbate a severe accident, the scope of intervention permitted to the State of Vermont must be sufficient to encompass issuon concerning this point.
l I In considering this issue, it must be recognized that there exist at least two potential accident sequence interactions which may result in this exacerbation. First, an accident commencing through events outsido the spent fuel pool (through common mode failuro or otherwise) may propagate and interact with the pool and spent fuel. Second, an 7
I accident commencing within the pool may be exacerbated by the '
pccconce there of greator number of spent fuel assemblios, 1
stored in the high density racks.
While the lack of availability of Commission staff documents up to this point has mado precise formulation of 1