Letter Sequence RAI |
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MONTHYEARML20199J4991998-01-29029 January 1998 Forwards Request for Addl Info Re Resolution of Unresolved Safety Issue A-46 Program at Plant.Requests Response within 60 Days of Date of Ltr Project stage: RAI ML20216K1711998-03-19019 March 1998 Informs That Util at Present Time,Coordinating W/Seismic Qualification Util Group,Industry Group Set Up Explicity to Address Issues Re Request for Addl Info for Resolution of USI A-46 Project stage: Request ML20205J2731999-03-0909 March 1999 Forwards Request for Addl Info Transmitted on 990224 to T Silko of Vermont Yankee Nuclear Power Corp.Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI Project stage: RAI 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 Project stage: Other 1998-03-19
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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: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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i January- 29, 1998 Mr. Donald A. Reid
-Senior Vice President, Operations Vermont Yankee Nuclear Power Corporation 185 Old Ferry Road Brattleboro, VT 05301
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING THE RESOLUTION OF UNRESOLVED SAFETY ISSUE A VERMONT YANKEE NUCLEAR POWER STATION (TAC N0, H59490)
Dear Mr. Reid:
By letter of July 1.1996 Vermont Yankee Nuclear Power Corporation provided the plant specific summary report in accordance with its commitment related to Generic Letter 87-02 regarding the resolution of the Unresolved Safety Issue (USI) A 46 program at Vermont Yankee Nuclear Power Station.
The NRC staff has reviewed the summary report, and, based on its review, finds that additional information, as outlined in the enclosure, is needed before we can complete our review of the report.
Please provide your responses within 60 days from the date of this letter. If you have any questions regarding this matter, please contact me at (301) 415-1496.
Sincerely, Original signed by KahtanN.Jabbour,SeniorProjectManager Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-271
Enclosure:
As stated g g fgg @@% j cc: See next page n
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DISTRIBUTION ' ' ' i p \
68 R. Eaton C. Hehl, RI d){c']' I PUBLIC K. Jabbour ACRS PDI-3 Rdg.
J. Zwolinski T. Clark D. Dorman OGC
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DOCUMENT NAME: G:\JABB00R\VERMTA46.RAI To receive a copy of this document, indicate in the box: "C" - Copy without attachment /erclosure "E" - Copy with attachment / enclosure "N" - No copy 0FFICE P0l*3/PN . , g ,t' Ib P013/LAjfj(/ l IE PDI 3 (/'h// l l NAME KJabbour NF" TClark ]/ b REaton ] I DATE 1/ 7 (-l /96 1/ / N /96 1/ 1 /96 DO 00b271 P PDR _
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D. Reid: Vermont Yankee Nuclear Power Station CC:
I
. Regional Administrator, Region.I Chii:f. Safety Unit i U. S. Nuclear Regulatory Commission Office of the Attorney General I 475 Allendale Road One Ashburton Place, 19th Floor-King of Prussia, PA 19406 Boston, MA 02108 1
Mr. David R. Lewis Mr. Peter LaPorte, Director Shaw, Pittman, Potts & Trowbridge ATTN: James Muckerheide 2300 N Street, N.W. Massachusetts Emergency Management Washington, DC 20037-1128 Agency 400 Worcester Rd.
-Mr. Richard P. Sedano. Commissioner P.O. Box 1496 Vermont Department of Public Service Framingham, MA 01701-0317 i 120 State Street, 3rd Floor Montpelier, VT 05602 Mr. Raymond N. McCanaless Vermont Division of Occupational i Public Service Board and Radiological Health i State of Vermont Administration Building 120 State Street Montpelier, VT 05602 Montpelier, VT- 05602 )
i Hs. Deborah B Katz Chairman, Board of Select.11en Box 83 Town of Vernon Shellburne Falls, MA 01370 P.O. Box 116 Vernon, VT 05354-0116 Mr. Gautam Sen Licensing Manager Mr. Richard E. McCullough Vermont Yankee Nuclear Power Operating Experience Coordinator Corporation Vermont Yankee Nuclear Power Station 185 Old Ferry Road
. P.O. Box 157 Brattleboro, VT 05301 Governor Hunt Road Vernon, VT 05354- Resident Inspector Vermont Yankee Nuclear Power Station G. Dana Bisbee. Esq. U. S. Nuclear _ RegulLtory Commission Deputy Attorney General P.O. Box 176 33 Capitol Street Vernon, VT 05354 Concord, NH 03301-6937 Mr. Jonathan H. Block, Esq.
Main Street
-P.O. Box 566 Putney, VT 05346-0566
REOUEST FOR ADDITIONAL INFORMATION VERMONT YANKEE NUCLEAR POWER STATION UNRESOLVED SAFETY ISSUE A-46 .
Docket No. 50-271
Reference:
Vermont Yankee letter, J. K. Thayer, to Document Control Desk (NRC).
dated July-1, 1996-(BVY 96-86), " Vermont Ytokee Summary Report for Resolution of USI A-46"
- 1. The conservatism of the seismi: margin methodology as described in EPRI NP-6041 report is not certain at this time. Its rpplication is, therefore, not endorsed by the NRC'for the analysis of safety-rflated systems and components, including the resolution of USI A-46 mechanical, electrical, and structural component outliers. You are requested to reevalJate the portion of your USI A-46 program, where the above methodology has been used, to ensure that all the outliers identified in Vermont Yankee A-46 program, are resolved by using methodologies that are consistent with the plant licensing basis or other approaches acceptable to the staff.
- 2. Section 9 provides a general discussion on the resolution of equipment and relay outliers identified in Table 5-4 and Table 8-1 of the Seismic Evaluation Report (attached to the reference stated above). -However, the discussion in Section 9 is very vague regarding the methodologies to be used and the status of this activity in the program. You are requested to provide the current status, and the percentage of completion, of the outlier resolution in your program. You
- are also requested to provide specific information regarding the approaches and methodologies used in the resolution of a representative sample of outliers listed in these tables.
- 3. The equipment outlier list provided in Table 5-4 does not include equipment
-located at elevations 303.00 ft. and 318.75 ft. of the reactor building and at elevation 300.00 ft. of the turbine building, where-spectral exceedances of in-
= structure response spectra (IRS) over 1.5 times the Bounding Spectrum were-indicated in Table-5-2. You are requested to clarify what equipment items are involved in these building elevations and how their seismic adequacy have been verified.
- 4. You stated in the Seismic Evaluation Report that the current schedule for completion of the outliers is prior to startup from_ the 1999 refueling outage.
You ara requested to provide the basis of detennining the operability of the affected systems while-a n'aber of safety-related components in the safe Enclosure
2 shutdown path have been identified as outliers: thus rendering their seismic adequacy questionable and their conformance to the licensing basis uncertain.
- 5. In Section 8.4 of the Seismic Evaluation Report, you stated that the list of essential relays does not include any low ruggedness (bad actor) relays. You are requested to explain where the " bad actor" relays are being listed. For all
" bad actor" relays identified, also explain how their contact chatter was determined to be. acceptable, as stated in the report.
- 6. Regarding the adequacy of seismic demand determination (ground spectra and in-structure response spectra), you are requested to address the following on a plant specific basis.
Referrina to the in-structure resoonse soectra orovided in your 120-day-resoonse to the NRC's reauest in Sunalement No 1 to Generic Letter (GL ) 97-02. dated May 22.
1992 the followino information is reauested.
- a. Identify structure (s) which have in structure response spectra (5% critical damping) for elevations within 40 feet above the effective grade, which are higher in amplitude than 1.5 times the Seismic Qualification Utility Group (500G) Bounding Spectrum,
- b. With respect to the comparison of equipment seismic capacity and seismic demand, indicate which mdthod in Table 4-1 of Generic Implementation Procedure (GIP-2) was used to evaluate the seismic adequacy for equipment installed on the corresponding floors in the structure (s) identified in Item (a) above. If you have elected to use method A in Table 4-1 of the
. GIP 2, provide a technical justification for not using the in-structure response spectra provic'1 in your 120 day response. It appears that some A-46 licensees are making an incorrect comparison between their plant's safe shutdown earthquake (SSE) ground motion response spectrum and the SOUG Bounding Spectrum. The SSE ground motion response spectrum for most nuclear power plants is defined as the plant foundation level. The 50VG Bounding Spectrum is defined at the free field ground surface. For plants located at deep soil er rock sites, there may not be a significant difference between the ground motion amplitudes at the foundation level and those at the ground surface. However, for sites where a structure is 4
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founded on shallow soil, the amplification of the ground motion from the foundation level to the ground surface may be significant.
- c. For the structure (s) identified in Item (a) above, provide the in-structure response spectra designated according to the height above the effective grade. If the in structure response spectra identified in the 120-day response to Supplement No.1 to GL 87-02 were not used, provide the response spectra that were actually used to verify the seismic adequacy of equipment within the structures identified in Item (a) above. Also, provide a comparison of these spectra to 1.5 times the Bounding Spectrum.
- 7. lne NRC staff has concerns about the way the A-46 cable trays and conduit raceways issue was being disposed of by licensees. The staff issued requests for additional information (RAI) to several licensees on this issue.
SOUG responded instead of the licensees because 50VG considered the RAI to be generic in nature. The staff issued a subsequent RAI to SOUG as a follow up to their response. However, the staff found that the correspondence with SOUG did not achieve the intended results in that they did not address the technical concerns of the staff. Therefore, we request that you address the following areas of staff concerns.
1he GIP procedure recommended performing what is called a limited analytic evaluation for selected raceways and cable trays. The procedure further recommended that when a certain cable tray system can be judged to be ductile >
and if the vertical load capacity of the anchorage can be established by a load check using three times the dead weight, no further evaluation is needed to demonstrate lateral resistance to vibration from earthquakes. .The staff has concerns with the manner in which these simplified GIP criteria were implemented at ycur plant.
The GIP procedure eliminates horizontal force evaluations by invoking ductility. However, all the so called non-ductile cable trays would ,
eventually become ductile by inelastic deformation, buckling or failure of the non-ductile cable tray supports and members. This proccdure is a basic departure from conventional methods of engineering evaluation and the GIP does not provide adequate bases for dealing with those cable trays that initially are judged to be non-ductile but are eventually called ductile by postulating failure of the lateral supports. If this procedure was followed for l
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eliminating cable trays for further assessment at your plant, then all'-the cable trays could conceivably be screened out from A-46 evaluation. We request
.that you r.espond to the following items to elicit information that would support our safety evaluation of cable trays at the Vennont. Yankee plant.
.(1) Provide.the total n'aber of raceways that were classified as ductile in your A-46 evaluation and for which you did not perform a horizontal load- "
. evacuation. Indicate the approximate percentage of such raceways as compared with the entire population of raceways. Discuss how the ductility concept is used-in your walkdown procedures.
(2). Provide descriptions of all the typical configurations of your ductile raceways (dimensions, member sizes, supports, etc.)
(3) Provide justification for stating that ductile raceways need not be evaluated for horizontal load. When a reference is provided, state the page number and paragraph. The reference should be.self contained, and not refer to another reference.
(4) In the evaluation of the cable trays and raceways, if the attachments are assumed to be ductile in one horizontal direction, does it necessarily follow that the same system is ductile in the perpendicular direction? If yes, provide the basis of this conclusion. if no, discuss how the seismic adequacy'of the. attachments was evaluated.
(5) Provide a definition of ductility:in engineering terms as used at Vermont Yankee for the USI A 46 evaluation. Clarify how this definition is applied to actual system configurations at Vermont-Yankee consistently for the purpose of analytical-evaluation. Provide an assessment of the maximum
' ductility utilized for the weakest cable tray support.
(6) JDiscuss any raceways and cable trays including supports in your plant that-are outside of the experience data. Explain what criteria are used for
- establishing their safety adequacy and.specify your plan for resolution ~ of
' outliers that did not meet;the acceptance criteria. Provide examples of '
the configurations of such raceways and cable trays including supports.
Also, indicate the percentage of cable trays and raceways outside the experience data in relation to the population of raceways 'and cable trays
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examined during the walkdowns of the safe shut down path. How are they .i o going to be. evaluated and disposed?
- 8. If Thermal-Lag panels are attached to a cable tray system, discuss how the changes'in weight have been incorporated in the GIP evaluation of these systems and their supports.
- 9. You stated that the reviews of the cable tray and conduit systems at Vermont Yankee were performed per the guidelines of Section II.8 of the GIP. However, the discussion provided in page 7-3 of the summary report regarding seismic i-supports appears.to differ from the GIP's description. Previde the basis for
- your deviation fros' the GIP.
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L10c You stated that toward the end of the plant construction phase after all the
- cable tray runs and related deadweight supports were installed, seismic
.' supports were added to the cable tray- runs in the Reactor Building (page 7-2).
Provide your evaluation of lateral seismic suppets and sample calculations as
. well as sketches or drawings.
You indicated that seismic supports of four cable trays were evaluated and they .
were found to have adequate margin for lateral seismic loads (Reactor Building.
elevation 252'-5") (page 7-3. summary report). Provide the evaluation of these supports'with adequate drawings or sketches.
- 11. You stated that rigid mount supports are used in isolated locations where trays n .are adjacent:to walls (page 7-1 of the summary report). You also indicated
' that cable trays with typically 24 to 26 feet long horizontal runs are
' laterally supported by seismic supports which are rigid mount frames e constructed of structural steel sections with welded connactions (Page 7-2),
Discuss how the supports are evaluated-and accepted. Clarify whether they are part of the outliers listed in Table 7-1 of the summary report. Provide sketches or drawings of the so called rigid supports and the calculations used for their evaluation.
l L 12.' Provide a sketch or drawing of the end anchor related to the cable tray system
?you discussed Lin Section 7.3 of-the summary report (page 7-3) and provide a calculation showing how this system and end conditions are evaluated and-accepted as adequate.
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- 13. -The summary report did not discuss anchor bolts except in relation to cable trays. Explain the absence of documented evaluations of anchorages for other equipment.
- 14. In the summary report you stateti that you were committed to implement the GIP-2, including the clarifications, interpretations, and exceptions in SSER 2, and to communicate to the NRC staff any significant or programatic deviations from the GIP guidance. You further stated that there are no significant or programmatic deviations from the GIP guidance.
Provide the worst-case items (from a safety point of view) which deviate from the GIP-2 guideline but were categorized as not being significant. In addition, we request that you clarify the definition of " safety significant" that the walkdown crew used: and provide the basis for why the definition is adequate.
- 15. You stated that resolution of the outliers continues. When the resolution is 4 complete, we request that you submit a completion report including the resolutions you discussed in the summary report.
- 16. Provide a clarification on the number of cable trays-evaluated: since the text indicates that 12 cable trays are evaluated for limited analytical review while Table 7-1 shows 13. Also, you discussed four cable trays in the Reactor Building, elevation 252, while Table 7-1 lists five cable trays. Explain this discrepancy.
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