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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:NRC TO U.S. CONGRESS
MONTHYEARML20247C3541989-03-17017 March 1989 Forwards Detailed Info Re Status of Implementation of TMI Action Plan Items at Listed Plants.Small Number of Action Items Still Need Resolution ML20236S5811987-11-19019 November 1987 Responds to Re Concerns for Adequacy of Notification of Plant Events to Town of Hinsdale,Nh. Response to Board of Selectmen for Town of Hinsdale Encl ML20215F0201986-12-17017 December 1986 Forwards Info Re Concerns Expressed by Constituent on Plant Safety,Per 861119 Request.Attention Directed by Commission, State of Vt,Licensee & Press to Capability of Mark I Containment Structure to Accommodate Severe Accidents ML20204F9361986-07-30030 July 1986 Responds to from R Blank,Addressing Concerns Re Safety of Older Nuclear Plants,Per SO Conte 860701 Request ML20062E9051982-07-19019 July 1982 Responds to Re Alleged Conditions Near Facility. Airborne & Waterborne Radioactivity Monitoring Programs Discussed.No Reason Exists to Believe That There Is Any Radiological Impact on Environ from Operation of Facility 1989-03-17
[Table view] Category:OUTGOING CORRESPONDENCE
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 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 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 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 ML20216F3171999-09-13013 September 1999 Forwards Insp Rept 50-271/99-06 on 990621-0801.One Violation Identified & Being Treated as Noncited Violation 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 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 ML20216D7321999-07-26026 July 1999 Forwards Insp Rept 50-271/99-05 on 990510-0620.Two Viiolations Being Treated as Noncited Violations ML20209G6931999-07-14014 July 1999 Forwards Request for Addl Info Re Spent Fuel Storage Capacity Expansion 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 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 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 ML20195J7221999-06-14014 June 1999 Forwards Insp Rept 50-271/99-03 on 990329-0509.Two Severity Level IV Violations Identified & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20195E1441999-06-10010 June 1999 Ack Receipt of Correspondence to NRC Commissioners Re Vermont Yankee Nuclear Power Station.Correspondence Forwarded to Staff for Appropriate Action ML20207G0921999-06-0404 June 1999 Forwards Insp Rept 50-271/99-04 on 990426-28.No Violations Noted.Insp Evaluated Performance of Emergency Response Organization During 990427,Vermont Yankee Nuclear Power Station full-participation Exercise ML20196J3001999-06-0404 June 1999 Informs That NRR Reorganized,Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Was Created. Reorganization Chart Encl ML20207E6001999-05-28028 May 1999 Forwards Operator Licensing Exam Rept 50-271/99-302 on 990510-11.Exam Addressed Areas Important to Public Health & Safety.Exam Developed & Administered Using Guidelines of NUREG-1021,Interim Rev 8.Both Applicants Passed Exam ML20207B8201999-05-25025 May 1999 Informs Licensee of Individual Exam Results for Applicants on Initial & Retake Exams Conducted on 990510-11 at Licensee Facility.Without Encls ML20206K1481999-05-0606 May 1999 Forwards Insp Rept 50-271/99-02 on 990215-0328.Three Severity Level IV Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20206J9951999-05-0505 May 1999 Informs That Util Authorized to Administer Initial Written Exams to Applicants Listed on 990510.Region I Operator Licensing Staff Will Administer Operating Test ML20206G6391999-05-0404 May 1999 Informs That Version of Holtec Intl Rept HI-981932 Marked as Proprietary Submitted by Util Will Be Withheld from Pubic Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20206E8641999-04-29029 April 1999 Forwards SER Concluding That Flaw Evaluation Meets Rules of ASME Code Concerning Util 990329 Request to Extend Reinspection Period for Jet Pump Riser Circumferential Weld Flaws Discovered During 1998 Refueling Outage ML20206A6871999-04-22022 April 1999 Informs of Completion of Review of Re Nepco in Capacity as Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee Atomic Power Co ML20205P1551999-04-0909 April 1999 Discusses 990225 PPR & Forwards Plant Issues Matrix & Insp Plan.Insp Program Subject to Rev ML20205K7461999-04-0808 April 1999 Advises That Info Contained in Holtec Intl Affidavit, Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20205K7531999-04-0707 April 1999 Discusses Alternative Proposal for Reexamination of Circumferential Welds in Plant Rpv.Nrc Has Determined That Alternative Proposal Meets Conditions in BWRVIP-05 Rept. Forwards Safety Evaluation ML20205J0331999-03-31031 March 1999 Informs That on 980423 NRC Oi,Region I Field Ofc,Initiated an Investigation to Determine Whether Williams Power Corp Employee,Working at Vynp,Had Been Threatened & Eventually Fired in April 1998 ML20204J4321999-03-19019 March 1999 Forwards from Ve Quinn to Cl Miller Forwarding IEAL-R/85-11, Vermont Yankee Nuclear Power Station Site- Specific Offsite Radiological Emergency Preparedness Alert & Notification Sys QA Verification, for Info ML20204D7481999-03-16016 March 1999 Forwards Insp Rept 50-271/99-01 on 990104-0214.No Violations Noted.Security Program Insp Found That Licensee Implementing Security Program That Effectively Protects Against Acts of Radiological Sabotage DD-99-04, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-04) Has Expired.Commission Declined Review.Decision Became Final Action on 990308.With Certificate of Svc.Served on 9903121999-03-11011 March 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-04) Has Expired.Commission Declined Review.Decision Became Final Action on 990308.With Certificate of Svc.Served on 990312 ML20207L5591999-03-0101 March 1999 Requests Addl Info in Response to Questions 6,7 & 11 of RAI Re GL 96-06 Program at Vermont Yankee Nuclear Power Station IR 05000271/19980141999-03-0101 March 1999 Forwards Request for Addl Info Based on Review of Util 961115 & 970313 Responses to GL 96-05 & Insp Rept 50-271/98-14 of GL 96-05 Program at Vermont Yankee Nuclear Power Station ML20207L5471999-02-26026 February 1999 Forwards Request for Addl Info for Ongoing Review of Vermont Yankee IPEEE Submittal Dtd 980630.RAI Related to Fire, Seismic,Internal Flooding & High Wind,Flood & Other External Event Areas ML20203H9791999-02-18018 February 1999 Forwards SER Accepting Licensee 970123 Info Supporting Util Determination That Exam Coverage Achieved During Reactor Pressure Vessel Shell Weld Insp Constitutes Alternative Which Provides Acceptable Level of Quality & Safety ML20203H7631999-02-12012 February 1999 Responds to 981120 Request for NRC Authorization to Perform Alternative Testing to That Specified by ASME BPV Code & Asme/Ansi, Code for Operation & Maint of Npps. Reviewed & Agreed That 990114 SER Needs Revision ML20203H8431999-02-11011 February 1999 Refers to 990201 Request for Withdrawal of 980501 Amend Request.Amend Request Superceded with Another Proposed Change to Ts.Informs That Commission Filed Encl Notice of Withdrawal of Application for Amend to FOL with Ofc of Fr ML20203D1691999-02-0505 February 1999 Acknowledges Inputs,Comments & Requests for Action Re Vermont Yankee Nuclear Power Plant,Provided by Electronic Mail Messages Dtd 990110-13 ML20202G2611999-01-28028 January 1999 Forwards Insp Rept 50-271/98-14 on 981122-990104.No Violations Noted.Nrc Initial Review of Scram Discharge Vol Drain Valve Failures Indicates That Licensee Design Change Process Was Not Effective ML20199K7081999-01-21021 January 1999 Forwards Corrected SE for Amend 163 Issued to FOL DPR-28 on 981228.Determined That Pages 2 & 3 of SE Required Clarification ML20199K6891999-01-20020 January 1999 Informs of Completion of Review of YAEC-1339 Re Allowing Use of FIBWR2 to Validate Reload Analyses Which Include New Fuel Rods & Varied Water Tube Designs.Forwards SE Concluding That Use of YAEC-1339 at Vermont Yankee NPP Acceptable ML20202C9551999-01-20020 January 1999 Informs That Licensee Has Been Authorized to Administer Initial Written Exam to Applicants as Listed on 990122. Operator Licensing Staff Will Administer Operating Test to Applicants ML20199L5901999-01-14014 January 1999 Forwards SER Accepting Util 981120 Request for Approval to Perform Alternative Testing to That Specified by ASME Boiler & Pressure Vessel Code,Section XI & Asme/Ansi OM, Operation & Maintenance of Nuclear Power Plants IR 05000271/19970131998-12-23023 December 1998 Forwards Insp Rept 50-271/97-13 on 981011-1121.No Violations Noted.Radioactive Liquid & Gaseous Effluent Control Programs Were Considered to Be Well Implemented ML20198S1661998-12-17017 December 1998 Final Response to FOIA Request for Documents.Records Encl & Identified in App C & D.App E Records Withheld in Part & App F Records Withheld in Entirety (Ref FOIA Exemption 5) & App G Records Withheld in Entirety (Ref FOIA Exemptions 4 & 5) 1999-09-30
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JUL 19 y n The Honorable Gordon J. liumphrey 7g United States Scnate _47 Washington, D.C. 20510
Dear Senator Humphrey:
Thank you for your letter of lune 21, 1982 addressed to Chaiman Palladino regarding concerns about the Vemont Yankee facility in Vernon, Vermont.
One of your constituents had provided you with a magazine article that made several allegations related to the proximity of the Vemont Yankee plant.
As a result of your request, we have looked into the thrust of the allega-tions raised in the article.
There are two concerns in our view: First is the allegation that the Vermont Yankee facility is releasing substantial quantities of radioactive material; second is the allegation that there are noticeable and direct of fsite effects attributable to Vement Yankee.
Federal regulations, 10 CFR 20, Appendix B, and 10 CFR 50, Appendix I, establish limits on the types and quantities of radioactive materials which may be released in effluents from nuclear power plants. 40 CFR 190 estab-lishes limits on both the projected annual radiation dose equivalent and total quantity of radioactive material entering the environment from the uranium fuel cycle. The 10 CFR regulations and the operating license issued by the NRC to the owner and operator of the Vernont Yankee facility require operable in-plant effluent nonitoring systems to measure and record radio-activity in the radioactive materials waste treatment and disposal systems as well as implementation of an onsite and of fsite radiologic ' environmental monitoring program.
In-plant effluent monitoring systems must meet specific operability and calibration standards established by the NRC. An NRC resident inspector is stationed at the Vemont Yankee facility and he routinely inspects and verifies the proper operation of these systems.
Vermont Yankee's environmental monitoring program includes analyses of i
airborne and waterborne radioactivity and direct radiation exposures. The airborne radioactivity monitoring program includes samples of milk, vegeta-t tion, food products and soil from several locations near the Vemont Yankee facility, including the liinsdale, New ilampshire area. The waterborne radio-
- activity monitoring program includes sanples of fish, aquatic vegetation, Connecticut River water and sediment, and ground water samples. Again, multiple sampics are taken during the year at various locations in New Hampshire, Vemont and liassachusetts. Direct radiation exposures are measured by thermoluminescent dosimeters (TLDs) which are placed by the licensee at twenty-one locations on and off the Vernont Yankee site. These devices provide a neasurement of the total radiation exposure, including natural background exposure at thase locatioris.
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The Honorable Gordon J. Hunphrey The results of analyses obtained from the environnental monitoring programs are evaluated and documented by the licensee. The licensee provides an ennu sl Radiological Environmental Report and a Semi-Annual [f fluent Release Report, as well as special reports, when required, to the NRC. These reports are placed in the fiRC's Public Document Room and are also reviewed by NRC regional office inspection specialists.
In addition to the actions taken by the licensee, the NRC also conducts its own measurenents to independently assess the licensee's results.
The (IRC progran provides for review of the licensee's sampling program and includes an independent measurements program whereby aliquots of etfluent samples are analyzed by the licensee, by our Region I office, and by a national laboratory. The results are compared to confirm the validity of the licensee's analytical techniques. In addition, the NRC places therno-luminescent dosineters at various locations near all nuclear power plants, including Vermont Yankee. The flRC first placed TLDs around the Vermont Yankee site in May 1930. There are 40 TLD locations around the site ranging j
from less than one to about nineteen miles away. To date, no exposures were measured which were above those which would be expected f rom natural back-I ground radiation.
In response to your request, reports from the licensee have been re-examined.
A review of the licensee's Semi-Annual Ef tluent Release Reports for the period 19/6 through 1981 indicates that the projected annual dose equivalent based on actual effluent and meteorological measurements did not exceed the environnental standards for the uranium fuel cycle (40 CFR 190). 40 CFR 190 specifies linits on both annual dose and total quantity of radioactive mterial entering the environnent f rom the uranium f uel cycle. Also, a review of the licensee's Annual Radiological Environmental Surveillance Reports for the period 1976 through 1981 indicates only a slight difference in the annual dose equivalent between environmental nonitoring stations which might be af fected by plant operations and background (control) stations not af fected by plant operations. In all cases, the difference in the annual dose equiva-lent was rauch less than the 40 CFR 190 limits. Additionally, the dose rates measured by the NRC during operation of the NRC's TLD Direct Radiation Network, and the enount of radioactive material in etfluents from the Vermont Yankee Nuclear Power Station actually measured by the NRC, support the licensee's conclusion. We have, theref ore, no reason to believe there is any radio-logical impact on the environment trom the operation of the Vemont Yankee facility.
The State or Venaont also monitors the environnent around Vernant Yankee and provides a monthly report to rur Region ! office. These reports reflect findings that releases of radioactivity from Vernont Yankee are very small (nuch less than penaitted) ar.o tnat levels of radioactivity in the environ-r.ent (air, water, particulates and milk) are not r;uch dif ferent than back-ground levels obtained prior to the operation of Vennont Yankee.
t
> ?
s The Honorable Gordon J. Humphrey With regard to the problems at the Fostyck fam, we understand that the New Hampshire State Department of Health and Welfare conducted radiation surveys in the vicinity of tne fam. We contacted Ms. Diane Tefft from the Bureau of Environmental Health who stated to us that they found no radiation levels above background. The Bureau routinely samples a fam contiguous to the Fostyck fam and has found no evidence of radiation above background. If you have any further questions,lis. Tefft will be happy to discuss them with you. She can be reached at 603-271-4588.
In addition, we contacted Dr. George Cilley, the l'ew Hampshire State Veterinarian, who stated that he had visited the Fostyck fam in April 1981 af ter receiving a call regarding premature and deformed calves. He stated that his impression was that the f am was not experiencing any more problems than fams elsewhere in the state. In his opinion, there was no evidence of particular problems related to Vemont Yankee. He can be reached at 603-271-2404 if you have f urther questions.
If, in the future, we identify any further information regarding the concerns discussed in your letter we will contact your office.
If I or my staff can be of any further assistance, please do not hesitate to contact me.
Sin
]stened)T. A.Rehm William J. Dircks Executive Director for Operations Distribution:
W. Dircks T. Rehm V. Stello i H. Denton l
R. DeYoung R. Minogue l G. Cunningham I
L. Underwood R. Haynes R. Starostecki l ED0 12043 l SECY-82-0662 PDR l LPDR i Docket No. 50-271 RI:RA ED0- 0,C4 I Region I Docket Room RHaynes WJD)rrJgt. p i .
OCA 7/g/82 7//f/82 l
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FINAL REPLY j . j f' ,} r .U, C CHAlHMAN Ctairman Palladino rlLE LOCATION g< gy t>rsen- $] CXECUT4VE DIRECTOH l O ESCRIPTION .]LLT1LR UMEMo O REWJRT O OTHEn SPECI AL INSTRUCTIONS OR REMARKS Rcq info about alleged conditions near Vermnt Yankee plant per attached magazine article fm constitutent CLASSIFIED DATA OOCUME NT/ COPY No. CLA%1FICATIONl NisunER OF PAGES CATEGOHY POS T A L H E GIS T R Y NO. O NSI O 90 0 FRO ASSIGNED TO. DATE INFORMATION ROUTING LEGAL REVIEW U FINAL O COPV h ynE5.f.29 7 _5/25/2?L Dircks ^"'"" ""
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