|
---|
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
[Table view] |
See also: IR 05000271/1997005
Text
_ . .
. . . . .
. . . .
..,
.- . j
.. ..
9,
!
November 20, 1997
!
Mr. Donald A. Reid l
Senior Vice President, Operations
Vermont Yankee Nuclear Power Corporation l
RD 5, Box 169 ,
Ferry Road i
Brattleboro, Vermont 05301
9
SUBJECT: NRC INSPECTION REPORT NO. 50 271/97 05 REPLY ,
,
Dear Mr. Reid:
This refers to your September 18,199' correspondence, in response to our letter dated, l
August 19,1997, regarding Vermont Yankee. This correspondence dealt with inspection
report 50 271/97-05and enclosed Notices of Violation 50 271/97-05 01 and 50 271/97- t
'
05-02.
,
'
We have reviewed this matter in accordance with NRC Inspection Manual Procedure
92901," Followup - Plant Operations." Based upon our preliminary review of your staff's
root cause determinations, the associated short and long-term corrective actions appear to
be appropriate. These actiono will be examined during future inspections to assess their
overall effectiveness. l
Your cooperation with us is appreciated.
Sincerely,
(1
ORIGINAL SIGNEJ BY:
}
Curtis J. Cowgill, Ill, Chief i
Projects Branch No. 5 l
Division of Reactor Projects
Docket No. 50 271 / ,
I
9712020031 971120 '
PDR ADOCK 0 71
a e < gAlt.algs!ss
.
1
'\
.
,.
_ ,, , m _ m ., ... ,,..y, _. _ , . _ .
- ._ .__. - . ... - ._. - . - - - - . - - - - . . . - . . _ . . - . _ - - - . - . _ -
. ... ;
,
.f !
Mr. Donald A. Reid 2
cc w/ encl: '
R. McCullough, Operating Experience Coordinator Vermont Yankee
R. Wanczyk, Director, Safety and Reguln+ory Aff airs
G. Maret, Plant Manager ,
J. Daffy, Licosing Engineer. Vermont Yankee Nuclear Power Corperation ;
'
J. Tilroy, Director, Vermont Public Interest Research Group, Inc.
- D. .tfft, Administrator, Bureau of Radiological Health, State of New Hampshire .
Chief, Safety Unit, Office of the Attorney General, Commonwealth of Massachusetts
D. Lewis, Esquire :
G. Bisbee, Esquire i
J. Block, Esquire :
T. Rapone, Massachusetts Executive Office of Public Safety ,
State of New Hampshire, SLO Designee
State of Vermont, SLO Designee
Commonwealth of Massachusetts, SLO Designee
D. Katz, Citizens Awareness Network (CAN)
Distribution w/ encl:
Region l Docket Room (with concurrences)
.UBLIC '
Nuclear Safety information Center (NSIC)
NRC Resident inspector
H. Miller, RA/W. Axelson, DRA
D. Screnci, PAO (2) *
G. Morris, DRS
C. Cowgill, DRP
D. Boarde, DRP
Distribution w/enci (VIA E MAIL): i
W. Dean, OEDO
K. Jabbour, NRR
S. Bajwa, NRR
R. Correia, NRR j
F. Talbot, NRR
inspection Program Branch, NRR (IPAS) e
DOCDESK i
>
,
DOCUMENT NAME: G:\ BRANCH 5\NOVR9705.CPC
To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "
E" =
Copy with attachment / enclosure * N" = No copy
OFFICE
NAME
Rl/DRP {
CJCOWGl".LA
( (b / l / l
l DATE l do M7' '
11/ /97
OFFICIAL RECORD COPY
.i
,
- .-. -
..-,,,n..,,--- g -ww,_..,_,. -,r- ,,-----.ye ,#-, ,,-
. .
. . -
,
Mr. Donald A. Reid 2
cc w/ encl:
R. McCullough, Operating Experience Coordinator Vermont Yankee
R. Wanczyk, Director, Safety and Regulatory Affairs
G. Maret, Plant Manager
J. Duffy, Licensing Engineer, Vermont Yankee Nuclear Power Corporation
J. Gilroy, Director, Vermont Public Interest Research Group, Inc.
D. Teff t, Administrator, Bureau of Radiologice':. alth, State of New Hampshire
Chief, Safety Unit, Office of the Attorney General, Commonwealth of M6ssachusetts
D. Lewis, Esquire
G. Bisbee, Esquire
J. Block, Esquire
T. Rapone, Massachusetts Executive Office of Public Safety
State of New Hampshire, SLO Designee
State of Vermont SLO Designee
Commonwealth of Massachusetts, SLO Designee
D. Katz, Citizens Awareness Network (CAN)
Distribution w/ encl:
Region I Docket Room (with concurrences)
PUBLIC
Nuclear Safety Information Center (NSIC)
NRC Resident inspector
H. Miller, RA/W. Axelson, DRA
D. Screnci, PAO (2)
G. Morris, DRS
C. Cowgill, DRP
D. Bearde, DRP
DistribydQD w/enct (VIA E MAIL):
W. Dean, OEDO
K. Jabbour, NRR
S. Bajwa, NRR
R. Correia, NRR
F. Talbot, NRR
Inspection Program Branch, NRR (IPAS)
DOCDESK
- _ .
. - . . . _ - - . _ _ - - - - . _ . - - - . .
.
. ~
VERMONT YANKEE ,
NUCLEAR POWER CORPORATION ,
s
.
9 h Ferry Road. Brattleboro. VT 05301-7002
{g
~
ENGINEERING OFFICE
$60 MAIN STR(ET
BOLToN. MA 01740
r
e
.
'
(608) 77M711
September 18,1997
BW 97117
"
United States Nuclear Regulatory Commission
ATTN: Document Control Desk .
Washington, D.C. 20555
References: (a) License No. DPR 28 (Docket No. 50-271)
(b) Letter, USNRG to WNPC, NRC Inspection Report 50 271/97 05 and Notice of
Violation, dated 8/19/97
Subject: Reply to a Notice of Violation . Inspection Report No. 50 271/97 05
This letter is written in response to Reference (b), which documents that certain of our activities were
not conducted in full compilance with NRC requirements. Ther.e violations, classified as Severity Level
IV, were identified during an NRC Inspection conducted from June 1 to JuY 19,1997. Our response
to the violations la provided below.
VIOLATION 1:
Technical Specification 3.7.A.7.b requires that, within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period subsequent to placing
the reactor in the RUN modo following a shutdown, the containment atmosphere oxygen
concentration shall be reduced to less than four percent and maintained in this condition.
Contrary to the above, the reactor was placed in the RUN mode t.t 8:20 p.m. on May 7,1997, but
atmosphere oxygen concentration in the torus alt space remained greater than four percent until
the morning of May 12,1997, a pe lod of approximately four and one half days..
RESPONSE TO VIOLATION 1
Reason For The Violation
Vermont Yankwe does not contest this vlotation.
The root cause of this everst was an inadeque'.e procedure which led to the use of Insufficient nitrogen
purge flowrate resulting in the torus not oeing inerted to less than 4%. Prior to this event the
procedure for inerting the primary ec.itainment was revised to require separate inerting of the
containment drywell and containment torus air volumes. The previous procedure revision allowed
Inerting of the torus and drywell volumes either simultaneously or sequentially.
- GiQ C ? 2KOf0 TJW
. .
/ VORMONT Y ANKOE NUCLE AR POWER CORPOR ATION
U.S. Nuclear Regulatory Commission
September 18,1997
Page 2
Contributing causes of this event, during Initial procedure development and subsequent revisions, were:
1. There was a lack of available technical basis Information which would have f acilitated a more
thorough assessment of tne procedure changes.
2. The failure on the part of the procedure writers and reviewers to obtain all the information
needed to support the procedure changes in the absence of available Information.
Corrective StsDe That Have Been Taken And The Results Achieved
1. Upon determination that oxygen concentrations were greater than technical specification
requirements, a reactor shutdown was initiated.
2. Troubleshooting activities were conducted and no significant primary containment air leaks
were located.
3. Containment inerting was agaln initiated and torus oxygen concentration was restored to less
than four percent.
4. The primary containment operating procedure which provides guidance for containment inerting
was revised as follows;
a. Additional guldance was added for establishing minimum inerting flowrates.
b. Additional guidance was added regarding the time required to inert to technical
specification requirements.
c. Instructions were added for monitoring drywell and torus pressures while inerting.
d. Instructions were added for obtaining grab samples to confirm that an oxygen
concentration of less than four percent has been attained.
5. An event report was initiated to document this event, determine the root cause, and corrective
actions.
Corrective Steo1That Will Be Taken To Avoid Further Violations
1. Vermont Yankee is revising the containment inerting calculation to optimize inerting times and
inerting purge flowrates that reflect the configuration of the nitrogen purge system and the
primary containment. This revision will provide a documented basis for inerting the drywell and
the torus volumes. This is expected to be complete by Nnvember 1997.
2. Based on the revised containment inerting calculation, Vermont Yankee will revise the primary
containment operating procedure and supporting design documents as necessary. This IP
expected to be complete by January 1998.
3. The ongo!w Design Basis Document (DBD) project will provide additional and more easily
retrievable d4 sign Information and beludes a validation of design requirements against
applicable implementing procedures. In addition, the procedure change process will be revised
to require the review of DBDs in addition to other reviews, to support any procedure changes.
This is expected to be complete by January 1998.
, ,
. .
!
'
VERMONT YANKEE NUC1. EAR POWER CORPOR ATION
U.S. Nuoloar R*gulatory Commission
September 18,1997 ,
Page 3 j
1
,
'
4. The event report will be provided to the Training Depattment for review by the Operations and
Engineering curriculum committees for inclusion as a lessons learned case study to reinforce
the need to verify or obtain technical lnformation to support procedure development or revision.
This is expected to be complete by April 1998.
i
Date When Full.Com9tlance Will De Achieved ,
Full compliance was achieved on 05/12/97 when torus oxygen concentration was returned to less than
four percent.
YlOLATlON 21
10 CFR 50, Appendix S, 'Ouality Assurance Criteria for Nuclear Power Plants and Fuel
Reprocessing Plants,' Critorion XVI, ' Corrective Actions ' states that, " measures shall be .
established to nasure that conditions. adverse to quality, such as failures, malfunctions,
deficiencies, deviations, defective material and equipment, and non conformances are promptly
identitled and corrected."
Contrary to the above, during the period June 1 to July 19,1997, the inspectors substantiated
that appropriate measures were not being implemented to assure prompt identification and ,
correction of tsoveral conditions adverse to quality, including:
,
1. five seismic hangers in the containment air dilution system that were found not to be
' I
property adjusted;
l
l 11. e ono-quarter inch gap that was found between the end battery cell and the seismic
'
support rock for one of 18 groups of cells in the "A" urcinterruptible power supply i
l
battery
lil, a conduit to class 1E junction box B 504 SI that was found to be missing the first unistrut
clamp from the junction box, and class 1E conduit 11188E S11 that was missing two
adjacent unistrut clamps; and,
iv. cracked caps that were found on the positive terminal of four celle in the un interruptible
power supply batteries indicating deterioration of the terminsi's electrolyte seals.
1
RESPONSE TO VIOLATION 2
Respon For The Ylolation
Vermont Yankee does oct contest this violation.
The conditions identified in the inspection report indicate that certain of our processes have a '
programmatic weakness in that they rio not force the complete restoration of the plant Systeins,
Structures and Components (SSCs) from maintenance and construction activities. In addition, we have >
determined that the threshold for questioning and identifying potentiel concerns and deviations from
structural, environmental and housekeeping requiremente was too high. The conditions identified by
the NRC inspectors were prcmotty addressed and resolved. However, Vermont Yankee's precesses,
programs and staff either d!d not identify them or, if previously identified and analyzed as acceptable,
_ _
, _ y, .. _, ___ , , ,,_ ,_ ,
. . l
~
7 VORMONT YANKEE NUCLEAR POWER CORPORATION
U.S. Nuclear Regulatory Commission
September IP,1997
Page 4
1
did not fully resolve the fletd conditions. The latter, allowed field conditions to exist which were either
continualty subject to question or fostered an environment and culture that assumed the conditions i
were acceptable. l
,
Based on the initial assessments Vermont Yankee has made to date, we do not believe that this issue
is indicative of a negatke trend in current performatice. The conditions noted are a result of past
practices for which new administrative direction and expectations are in place to adequately address
or prever i the problems.
Corrective Steps That Have Been Taken And The Results Achieved
Based on the trend of material condition issues identifled by the NRC Resloent inspector and
recognizing that it has been Vermont Yankee's expectation that VY staff also identify such issues,
Vermont Yankee commissioned a multi-disciplined task team to systematically assess the existing
material condition of the plant. This naam was organized, trained and a detailed Inspection plan and
schedule was prepared and initiated on July 29,1997. All safety related plant areas accessible during
plant operation (34 distinct areas) have been inspected with additional deficiencies / concerns identified.
All discrepancies have been ident! fled in Vermont Yankee's Work Order Request process and the
corrective action process, if appropriate. This action is complete.
Corrective Steps That Will Be Taken To Avold Further Violations
1. The task team will continue to evaluate the discrepancies identified in the systematic material
condition inspection to determine if they are indicative of any weakness in our work control and/or
implementation processes, if weaknesses are identified, additional event reports will be generated.
This la expected to be complete by October 1997.
.
2. The responsible departments will evaluate the causes of these issues and initlate corrective actions
to address any identified weaknesses. Management will ensure that all personnel are aware of
Vermont Yankee's expectation for the material condition of the plant. Estimated completion of these
l
evaluations and the resultant implementation of corrective actions is projected to be completed by
l
December 1997,
3. The task team w!!! track and ensure the evaluation, disposition and resolution of the
discrepancies / concerns identified in the systumatic material condition assessment. Allitems that r:an
t
be immediately resolved will be, via the appropriate process. The majority of the other items will be
! corrected by Work Orders, scheduled for completion at the earliest available system work week. By
i
'
October 1997, tracking items will be added to Vermont Yankee's Corrective Action Program for the
remaining discrepancies,
l 4. The System Enginaering Program Document will be modified to take advantage of the training and
i experience gained by the System Engineers in conducting these systematl0 walkdowns. Quarterly,
! system and structure walk downs will be conducted by all system engineers. This process will provide
verificatlin of the effectiveness of corrective actions implemented via items 2 and 3 above. This is
expected to be complete by November 1997.
5. Safe *y related plant areas that are not accessible during plant operation will be similarly inspected
prior to startup from the next refueling outage. This is expected to be completed by May 1998.
I
1
-.__ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ - _ _ . - - _ _ _ _ _ _ _ _
e e
~
s' VERMONT YANKEE NUCLEAR PowEn CORPORATION
U.S. Nuoiser Regulatory Commission
. September 18,1997
Page5
y
l
l
Date When Full Comol'ance Will se A thieved
Corrective actions required to address Von iont Yankee's programmatic weaknesses and threshol.1 for j
identifying material oo edition deficiencies wJ' be completed by 12/31/97. Resolution of the additional i
identitled deficiencies concems will be completed commensurate with their safety significance and the I
plant work schedules.
1
AdditionalInformation ;
in the course of reviewing eves.3 per M event report process, human performance, procedure quality,
commonloations, and work practk.g have been recently identified and acknowledged as areas needing j
inoroased management oversight snC Involvement. . Vermont Yankee does not believe recent
p performance issues identifled are i.Mative of an overall adverse performance trend. Station
management continues to foster a low threshold for initiating event reports. Consequently, the quantity ;
4
of event reports has increased significantly and has resulted in identifying an adverse precursor
performance trend similar to those identified in Reference (b). Senior management has and continues
to provide strong day-to day involvement in the corrective action process resulting in early identification ;
of adverse perfonnance trends and development of commensurate corrective actions. '
,
!
i Senior plant management has established en action plan for improving human performance at Vermont
Yankee. input into the action plan was discussed with all sentar Vermont Yankee managers in a
workshop on July 23 24,1997. A senior manager has been assigned responsibility to implement this
action plan. The plan will be Initiated in October 1997 and is considered a priority initiative by senior
'
management. The Vermont Yankee Observation Program is also being modified to emphasize human .
performance during field observations. We have also recently developed and implemented a Stop,
Think, Act and Review (STAR) laboratory. This training has been provided to limited plant staff. We -
anticipate wider application of this important training in the future. We are confident these initlatives
will result in improved human performance. Also, we continue to look for negathe trends through our
correctiv!, action process and apply corrective actions focused on improving performance.
in Reference @) you also requested information regarding any additional actions associated with the ,
l manipulation of a wrong hydraulic control unit drain valve by the plant operating staff, in addition to
the human performance initiatives, observation program improvements, and STAR training described
i i
above a human factors review of the hydraulic control unit alarm panel will be performed. This review
will consider lines of demarcation, labels engraved with arrows indicating the appropriate push button, !
, and any additional operator aids needed. Following this review any necessary modifications to the
l hydraulic control unit alarm panel will be performed. This is expected to be complete by April 1998.
We trust that the enclosed information is responsive to your concems; however, should you have any
!
,
questions or require additionalinformation, please do not hesitate to contact us.
(
Sincerely,
,
2
I
VERMONT YANKEE NUCLEAR POWER CORPORATION
'
s
I
l s
'
Donald A. Reid
Senior Vice President, Operatiens
CC: USNRC Region I Administrator -!
. USNRC Resident inspector VYNPS >
USNRC Project Manager VYNPS _
._ !
i .
.. -
?