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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 ML20217C1051999-10-0808 October 1999 Forwards Amend 153 to License DPR-3 & Safety Evaluation. Amend Revises TS Section 6.0,Administrative Controls,By Deleting TS Sections 6.2.2.f Which Contains Limits on Working Hours of Plant Staff 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 ML20212J2231999-10-0101 October 1999 Forwards Copy of Environ Assessment & Fonsi Re 990317 Application for Amend to Revise TS Section 6.0 by Deleting TS Section 6.2.2.f Which Contains Limits on Working Hours of Plant Staff 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-99-113, 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-99-114, 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-99-121, 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-99-115, Forwards non-proprietary & Proprietary Responses to 990714 RAI Re Civil & Mechanical Engineering Considerations for Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355.Proprietary Encls Withheld1999-09-16016 September 1999 Forwards non-proprietary & Proprietary Responses to 990714 RAI Re Civil & Mechanical Engineering Considerations for Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355.Proprietary Encls Withheld BVY-99-118, Responds to RAI Concerning GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions1999-09-16016 September 1999 Responds to RAI Concerning GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions 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 ML20211J5001999-08-31031 August 1999 Forwards Proposed Rev 29 to Yankee Decomissioning QA Program, for NRC Info & Approval.Yaec Requests That Rev 29, Dtd May 1999 & Originally Transmitted in Be Withdrawn from Further Consideration by NRC Staff ML20211J2711999-08-27027 August 1999 Forwards Amend 152 to License DPR-3 & Safety Evaluation. Amend in Response to Application Dated 990324,deletes License Condition 2.C (10) Which States: Licensee Shall Maintain FFD Program IAW Requirements of 10CFR26 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 ML20216F1891999-08-26026 August 1999 Forwards Copies of Maine Yankee & Yankee Rowe Refs Listed, Supporting Industry Position That Branch Technical Position Asb 9-2 Methodology over-estimates Spent Fuel Decay Heat 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 ML20210S0621999-08-10010 August 1999 Forwards semi-annual fitness-for-duty Program Performance Data for six-month Period of 990101-990630,IAW 10CFR26.71(d) ML20210R1421999-08-0404 August 1999 Forwards Insp Rept 50-029/99-02 on 990411-0714.One Severity Level 4 Violation Occurred,Being Treated as NCV 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 ML20210G4271999-07-27027 July 1999 Forwards Testing Data & Associated Results for Fitness for Duty Program at Plant for 990101-0630 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 ML20216D7321999-07-26026 July 1999 Forwards Insp Rept 50-271/99-05 on 990510-0620.Two Viiolations Being Treated as Noncited Violations ML20210F3691999-07-21021 July 1999 Submits Response to NRC Request for Clarification of Certain Details of Yaec Proposed Mods to Yankee Nuclear Power Station Defueled TS 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 ML20209G6931999-07-14014 July 1999 Forwards Request for Addl Info Re Spent Fuel Storage Capacity Expansion ML20209J0601999-07-14014 July 1999 Forwards Rev 11 to Vols 1-10 of State of Nh Radiological Emergency Response Plan & Vols 11-50 to Town Radiological Emergency Response Plans,In Support of Vermont Yankee & Seabrook Station.Vols 17-19 of Were Not Included ML20209G1531999-07-12012 July 1999 Discusses Util Setpoint Control Program Implementation Schedule,As Committed to in Licensee 990514 Response to Notice of Violation,Insp Rept 50-271/97-10 ML20209D4881999-07-0909 July 1999 Forwards Rev 29 to Decommissioning QA Program, for Info & NRC Approval,Iaw 10CFR50.54(a)(3).Attachment a Provides Listing of Changes,But Does Not Discuss All Refomatting, Grammatical,Editorial or Typographical Changes ML20209C3151999-07-0101 July 1999 Forwards Rev 9 to Security Plan,Reflecting Plant Decommissioning Activities & Continues to Provide Protection Against Radiological Sabotage.Rev Withheld 1999-09-30
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062G6581990-11-20020 November 1990 Documents 901011 drop-in Meeting Re Refueling Outage Progress,Recent Allegations & NRC Insps ML20062F2731990-11-20020 November 1990 Forwards Request for Response to Allegation NRR-90-A-0050. Encl Withheld (Ref 10CFR9.17 & 9.21) ML20062F3681990-11-14014 November 1990 Forwards Safeguards Insp Rept 50-271/90-11 on 900829-31 & Notice of Violation ML20058G4961990-11-0808 November 1990 Advises That Maint Activity for Control Rod Relatch Witnessed by NRC on 901104.Activity Successful ML20197H6971990-11-0606 November 1990 Forwards Resident Safety Insp Rept 50-029/90-16 on 900821- 1001 & Notice of Violation ML20058F2151990-11-0202 November 1990 Forwards Safety Evaluation Accepting Util Responses to Generic Ltr 83-28,Item 1.2, Post-Trip Review - Data & Info Capability ML20058F2601990-10-31031 October 1990 Forwards Ref Matl Requirements for Reactor Operator Licensing Exams Scheduled for Wk of 910211 ML20058D3501990-10-30030 October 1990 Forwards Safety Insp Rept 50-029/90-17 on 900730-0803. Unresolved Items Noted ML20058E0791990-10-26026 October 1990 Advises That NRC Will Perform fitness-for-duty Program Insp. Util Written Policies & Procedures Requested ML20058D2411990-10-26026 October 1990 Requests Written Policies & Procedures Required by 10CFR26.20 Providing Background for fitness-for-duty Insp ML20058D2651990-10-23023 October 1990 Forwards Insp Rept 50-271/90-80 on 900806-17 & Notice of Violation ML20058C3901990-10-22022 October 1990 Forwards Amend 137 to License DPR-3 & Safety Evaluation. Amend Modifies Surveillance Requirement 4.1.3.4 ML20062B8901990-10-19019 October 1990 Forwards one-time Exemption from 10CFR55.59(c)(3)(i)(A)-(L) Re Annual Operator Simulator Training ML20058D2811990-10-19019 October 1990 Discusses Violations Noted in Insp Rept 50-029/90-14 & Forwards Notice of Violation ML20058B5511990-10-18018 October 1990 Advises That 900922 Response to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-08,Item 2.2 Part 2, 'Vendor Interface for Safety-Related Components,' Acceptable ML20062B6981990-10-12012 October 1990 Extends Invitation to Participate in 910220 Symposium & Workshop in King of Prussia,Pa Re Engineering Role in Plant Support ML20062B8671990-10-12012 October 1990 Extends Invitation to Attend 910220-21 Util Symposium/ Workshop in King of Prussia,Pa Re Engineering Role in Plant. Interest to Participate,Intent to Attend & Approx Number of Representatives to Attend Requested by 901115 ML20059P0161990-10-12012 October 1990 Advises That 900920 Response to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2 Part 2, 'Vendor Interface for Safety-Related Components,' Acceptable ML20059N7121990-10-10010 October 1990 Responds to Util Re Discovery of Flaws in Feedwater Check Valves 27B & 96B.NRC Believes Valve 96B Should Be Reinspected at Next Reload Outage to Verify Util Fracture Mechanics Analyses ML20059N4801990-10-0303 October 1990 Forwards Maint Team Insp Rept 50-029/90-81 on 900709-20 & 0806-10.Weaknesses & Unresolved Item Noted ML20059N1351990-09-28028 September 1990 Forwards Safety Insp Rept 50-271/90-09 on 900703-0812 & Notice of Violation ML20059M0511990-09-26026 September 1990 Forwards Corrected Pages to Amend 136 to License DPR-3 ML20059M5301990-09-25025 September 1990 Forwards Safety Insp Rept 50-029/90-12 on 900619-0820. Violations Noted But Not Cited IR 05000271/19900061990-09-14014 September 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-271/90-06 ML20059H5671990-09-12012 September 1990 Advises That NRC Terminated Review of YAEC-1710, Yankee Nuclear Power Station Pilot Evaluation Rept for Plant License Renewal, Per Util 900716 Request.Resolution of Issues Will Occur as Part of Review of Application ML20059J2411990-09-12012 September 1990 Advises That 900828 Revised Diesel Generator Test Plan for Qualification & Preoperational Testing Acceptable.Tech Spec Changes to Enable Util Achieve Credit for Increased Generator Capacity Will Be Considered When Proposed ML20059K7111990-09-10010 September 1990 Forwards Insp Rept 50-029/90-14 on 900802-27.Enforcement Conference Scheduled for 900921 ML20059H0601990-09-0707 September 1990 Discusses Unescorted Access to Licensee Facilities & fitness-for-duty Program,Per .Nrc Regulations Do Not Prohibit Licensee from Accepting Access Authorization Program of Another Licensee,Contractor or Vendor ML20059G2231990-09-0606 September 1990 Forwards Amend 135 to License DPR-3 & Safety Evaluation. Amend Modifies Tech Spec Surveillance Requirement 4.5.2a to Change ECCS Pump Surveillance Frequency from Monthly to Quarterly ML20059E3011990-08-31031 August 1990 Forwards Safety Assessment of Yae 1735, Reactor Pressure... Evaluation Rept for Yankee Nuclear Power Station, Submitted w/900705 Ltr.Nrc Calculations Recognizing Uncertainties Conclude That Plant May Operate Until Feb 1992 ML20058P0701990-08-0909 August 1990 Forwards Insp Rept 50-029/90-11 on 900619-22.No Violations Noted ML20058M6221990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Encourages Initiation of Initiative Similar to Region V Licensees Establishment of Engineering Mgrs Forum to Foster Disciplined & Coordinated Approach to Initiatives ML20058N0681990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Cooperative Effort Would Promote Efficiency & Enhance Effectiveness of Nuclear Power Plant Activities ML20056A9341990-08-0303 August 1990 Forwards Radiological Safety Insp Rept 50-029/90-13 on 900709-13.One Noncited Violation Noted ML20056A9311990-08-0202 August 1990 Forwards Safety Insp Rept 50-271/90-08 on 900716-20.No Violations Noted ML20058L5981990-08-0202 August 1990 Forwards Amend 134 to License DPR-3 & Safety Evaluation. Amend Incorporates NRC Guidance in Generic Ltr 88-17 to Facility Tech Specs.Three New Tech Specs Added & Change Also Addresses Low Temp Overpressurization ML20058L0241990-08-0202 August 1990 Forwards Amend 133 to License DPR-3 & Safety Evaluation. Amend Incorporates Wording from Std Westinghouse Tech Specs Into Util Limiting Condition for Operation Specs 3.10.3 & 3.10.4 ML20058L5331990-08-0202 August 1990 Forwards Rept from NRC Consultant Gr Odette Re Yankee Rowe Reactor Vessel Integrity.Response Requested by 900806 ML20055J4861990-07-31031 July 1990 Requests Performance of PTS Probablistic Analysis Using Broad Range of Matl Properties Re Reactor Pressure Vessel Evaluation Rept ML20055J2651990-07-27027 July 1990 Forwards Request for Addl Info Re Yankee Rowe Severe Accident Closure Submittal.Questions Concern Individual Plant Exam,Containment Performance Improvement Program & Accident Mgt.Response Requested within 1 Month ML20056A4021990-07-25025 July 1990 Forwards Radiological Controls Insp Rept 50-271/90-06 on 900618-22 & Notice of Violation ML20058L4761990-07-25025 July 1990 Forwards Exam Rept 50-029/90-06OL on 900619-21 IR 05000029/19890801990-07-25025 July 1990 Ack Receipt of Re Violations Noted in Insp Rept 50-029/89-80 ML20055H0011990-07-17017 July 1990 Confirms 900703 Telcon W/J Pelletier & J Durr Announcing SSFI to Be Conducted at Facility During Wks of 900806 & 17. Requests Info Listed in Encl 1 Forwarded No Later than 900720 ML20055G7991990-07-16016 July 1990 Forwards Safety Insp Rept 50-029/90-09 on 900515-0618.No Violations Noted ML20055C8531990-06-18018 June 1990 Forwards Amend 132 to License DPR-3 & Safety Evaluation. Amend Changes Title of Technical Svc Supervisor & Establishes New Positions Entitled Maint Support Supervisor & Operations Support Supervisor 1990-09-07
[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 ML20217C1051999-10-0808 October 1999 Forwards Amend 153 to License DPR-3 & Safety Evaluation. Amend Revises TS Section 6.0,Administrative Controls,By Deleting TS Sections 6.2.2.f Which Contains Limits on Working Hours of Plant Staff 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 ML20212J2231999-10-0101 October 1999 Forwards Copy of Environ Assessment & Fonsi Re 990317 Application for Amend to Revise TS Section 6.0 by Deleting TS Section 6.2.2.f Which Contains Limits on Working Hours of Plant Staff 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 ML20211J2711999-08-27027 August 1999 Forwards Amend 152 to License DPR-3 & Safety Evaluation. Amend in Response to Application Dated 990324,deletes License Condition 2.C (10) Which States: Licensee Shall Maintain FFD Program IAW Requirements of 10CFR26 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 ML20210R1421999-08-0404 August 1999 Forwards Insp Rept 50-029/99-02 on 990411-0714.One Severity Level 4 Violation Occurred,Being Treated as NCV 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 ML20209G6931999-07-14014 July 1999 Forwards Request for Addl Info Re Spent Fuel Storage Capacity Expansion 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 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 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 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 ML20207D8131999-05-27027 May 1999 Discusses Reorganization of Nrr,Effective 990328.Forwards Organizational Chart 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 ML20206R3221999-05-0505 May 1999 Forwards Insp Rept 50-029/99-01 on 990101-0411.No Violations Noted.Activities at Rowe Facility Generally Characterized by safety-conscious Operations to Maintain Spent Nuclear Fuel & Careful Radiological Controls to Workers 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 ML20205L0701999-04-13013 April 1999 Grants Voluntary Extension to Allow CAN to Effectively Participate in Hearing Process (ASLBP 98-736-01-LA-R).With Certificate of Svc.Served on 990413 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 ML20207F8791999-03-0505 March 1999 Forwards Amend 151 to License DPR-3 & Safety Evaluation. Amend Revises Pol by Changing Submittal Interval for Radioactive Effluent Repts from Semiannual to Annual ML20207H8981999-03-0303 March 1999 Responds to Concerns Raised in Petitions to Intervene Filed with NRC by Necnp on 980224 & Citizens Awareness Network on 980226.Petitioners Requested Hearing on NRC Staff Consideration of License Termination Plan for Yankee Plant 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 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 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 1999-09-30
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Docket No.50-029 Yankee Atomic Electric Company ATTN: ~Mr. Bruce L. Drawbridge Vice President and Manager of Operations 580 Main Street
. Bolton, Massar:husetts 01740-1398 Gentlemen:
Subject: Inspection Report No. 50-029/89-14 and 50-271/89-10 This letter refers to the routine inspection conducted by Mr. T. Rebelowski and Mr. R. Winters of'this office on July 17-21, 1989 at the corporate office in Bolton, Massachusetts and at the plant sites in Rowe, Massachusetts and Vernon, Vermont. The results of the inspection were discussed with Dr. A. Kadak, at Bolton, with Mr. St. Laurent at the Yankee Rowe plant and with Mr. Pelletier of the Vermont Yankee plan This inspection was directed at activities related to engineering support provided to the plants by the corporate engineering staff. Areas examined are described in the NRC Region I Inspection Report which is enclosed with this letter. Within these areas, selected examinations of procedures and representative records, interviews with personnel, and observations by the inspectors were mad Within the scope of this inspection, no violations were observe No reply.to this letter is required. Your cooperation with us in this matter is appreciate
Sincerely, Ori t:iral Signed By1 Jact;ue P. Durr
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Jacque P. Durr, Chief l Engineering Branch Division of Reactor Safety
Enclosure:
NRC Region I Inspection Report No. 50-029/89-14 and 50-271/89-10 l
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0FFICIAL RECORD COPY IR 50-029/89-14 - 0001. /10/89 8909110316 890831 PDR Q
ADOCK 05000029 PDC 3 '<)/ I\
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REGION I==
Report No /89-14 50-271/89-10 Docket No License No DPR-3 -
DPR-28
~ Licensees: Yankee Atomic Electric Company 580 Main Street Bolton, Massachusetts 01740 Vermont Yankee Nuclear Power Corporation RD 5, Box 169, Ferry Road Brattleboro, Vermont 05301 Facility Names: Yankee Nuclear Power Station Vermont Yankee Nuclear Power Station Inspection At: Bolton, Massachusetts Rowe, Massachusetts Brattleboro, Vermont Vernon, Vermont Inspection Dates: July , 17-21, 1989 Inspectors: W / M T. RebelowsKi, Senior Reactor Engineer, OPS, '
date 08, DRS, Region I hu R. W. Winters, Reactor Engineer, MPS, EB, T 1 %
date DRS, Region I Approved by: 2kmh de/M 6// SIB 9 p J. R. Itrosnidet, Chief, MPS, date Engineering Branch, DRS, RI Inspection Summary: Routine announced inspection on July 17-21,1989 (Report Nos. 50-029/89-14 and 50-271/89-10)
Areas Inspected: Corporate engineering and offsite support for the plants and implementation of modification Results: No violations or deviations were identifie N ;
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DETAILS 1.0' Persons' Contacte Yankee Atomic Electric Company, Bolton, Massachusetts R. Berry, Assistant to Vice President Operations B. Drawbridge, Vice President and Manager of Operations D.-Hansen, Director, Plant Engineering Department
. (1) 'J. Haseltine, Project Director, Yankee Project (1) J. Hoffman, Engineering Manager, Vermont Project
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-(1) W. Jones, Engineering Manager, Yankee Project (1) A.- Kadak, President, Yankee Nuclear Power Corporation
. Mcdonald, Manager, Quality Service Grou (1) S. Miller, Project Manager, Vermont Project J. Robinson, Director, Environmental Engineering A. Shepard,' Director, Quality Assurance
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(1) J. Thayer, Project Manager, Yankee Project Yankee Atomic Electric Company, Rowe, Massachusetts
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J. Falconieri, Maintenance Engineer (2) -T..Henderson, Assistant Plant Superintendent (2) J. Kay, Technical Services Manager
'(2) D. King, Maintenance' Support Supervisor
~(2)_ R.-Mellor, Technical Director (2) R. Mitchel1, Maintenance Manager (2) -N. St. Laurent, Plant Superintendent Vermont Yankee Nuclear Power Corporation
- K. Casey, Manager, Employment and Compensation R. Grippardi, Supervisor, Vermont Yankee Quality Assurance' (YAEC).
R.'Lopriore, Maintenance Supervisor M, Mete 11, Engineering Support Supervisor (1,3)J. Pelletier, Plant Manager, Vermont Yankee D. Reid, Manager, Operations Support .
T. Schimelpfenig, Director, Procurement and Information Systems D. Stafford, Technical Training Supervisor United States Nuclear Regulatory Commission-(2) M. Markley, Resident Inspector, Yankee Rowe,
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(1) Denotes those attending the exit meeting July 19, 1989 in Bolton, Massachusetts (2) Denotes those attending the exit meeting July 21, 1989 in Rowe, Massachusetts (3) Denotes those attending the exit meeting July 21, 1989 in Brattleboro, Vermont L- _ _ - _ - _ _
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L The' inspectors also contacted other administrative and technical personnel during the inspectio .0 Objectives The objectives of this inspection were to assess the adequacy of the licensee's program for engineering support of plant operations including design and configuration control, interfaces with other internal and external organizations, management support, staffing levels and experience, training, procurement, Quality Assurance, and responses to NRC requirements and request .0 Licensee Commitments The licensee's commitments and documents reviewed are listed in Attachment "A" to this repor .0 Yankee Atomic Electric Company (YAEC)
.The Yankee Rowe plant is operated by YAEC and is located on the Deerfield River in Rowe, Massachusett The plant was placed in commercial optration in 1961 and has been in full operation since that time except for maintenance and refueling shutoowns. The unit is rated at 185 megawatts (gross).
The Vermont Yankee plant is operated by the Vermont Nuclear Power Corporation and is located on the Connecticut River in Vernon, Vermont. The plant was placed in commercial operation in 1972. In 1988 the plant operated with a capacity factor of 93%. The unit is rated at 626 megawatts (gross).
In 1968, the Securities and Exchange Commission authorized YAEC to organize a Nuclear Services Division (NSD) under the Company's corporate structur The Nuclear Services Division bas a staff of approximately 400 engineers who provide engineering services in all aspects of nuclear power plant construction and operation including Nuclear Engineering, Environmental Engineering, Operations, Quality Assurance, Plant Engineering and Fuel Management. Services are performed on a cost basis for the Yankee Rowe plant, Vermont Yankee, Maine Yankee, and Seabrook. YAEC is a small utility with total employment of approximately 700 people including the 200 assigned to the operation of Yankee Row .0 YAEC Organization YAEC is organized into two Divisions, one is Plant Operations Division consisting of the Yankee Rowe plant, the other is Yankee Nuclear Services Division (YNSD) that includes the balance of the organization. YNSD consists of eight major functions that provide services to the operating plants. These services include the following:
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O ~*- _ Projects - Reporting to a Vice' President-Yankee Rowe i;
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- - Quality Assurance I Quality Services Audits
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- En'v ironmental Engineering
- ' _ Material Management and Control Purchasing i Fuel Management Cost Control -l Legal ;
- Finance and Administration Accounting
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6.0 Projects Organization j i
The inspectors interviewed YAEC management and staff personnel and reviewed personal qualification records to determine that individuals were qualified ,
to perform the assigned functions. In the YNSD organization a Project i )
> defined as the engineering section assigned responsibility for engineering l services to a plant. Each Project is organized with a Project Manager and !
Engineering Manager. The Projects are further divided into disciplines, i e.g. systems, mechanica1' instrumentation and control, and electrical that
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complement the-requirements of the plants. The performance of the work is {
controlled by individual Project Manuals that' encompass both administrative and engineering' function l
. Requests for support from the plants are received by the Project Manager j and may include design changes, safety evaluations., contractor services, '
and other engineering support required. When a request is received by the ,
Project Manager it is initially reviewed to determine the safety significance, j cost', schedule, and impact on the plant. After initial review, meetings !
are held with the requester to establish the-priority, scope, and schedule for each request. Engineering support'is followed by the assigned Project
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u l The-inspectors determined that'the engineers in the Project organizations were. qualified in.accordance with ANSI 18.1 in the appropriate discipline For example, in the Vermont Yankee Project organization the 27 engineers-held 39 engineering degrees and had an average of approximately 11 years of nuc1' ear experienc Personnel turnover was very low (approximately ,1%)
in the YAEC organization indicating a stable workforce and continuity of-engineering' service Plant Life Extension Program (PLEX)
The inspectors discussed the PLEX program with management personnel and determined that the initial studies indicate that obtaining data for the reactor pressure vessel is the first ;,riority. The operating license for the Yankee Rowe plant is scheduled to expire July 9, 2000. YAEC was awarded a. combined Electric Power Research Institute (EPRI) and Department of Energy (DOE) contract to participate as the lead PWR to demonstrate the feasibility of. operating. nuclear. plants beyond their 40 year operating licenses. As result, the-licensee has established a group of approximately 20 engineers supplemented by an equal number of contracted engineers to establish the feasibility of extending the plant life for another 20 year Conclusions The organization of engineering services into Projects, each responsible for' service to'a specific plant provides continuity for the plant Each Projects group was organized by engineering discipline and was well staffed-with experienced and knowledgeable engineers. The low turnover of engineer-ing talent assures continuity of the services provided to the plants and reduces'the training required to maintain proficiency in the YAEC method The establishing of the PLEX program is a major undertaking for a utility the size of YAEC. -While the contract with EPRI and DOE is valuable, YAEC will'be required to fund approximately half the total cos .0 Quality Assurance The Quality Assurance (QA) organization reports through a Director to the YAEC President. The inspectors reviewed selected audit reports and inter-viewed individuals to determine the quality and adequacy of audits and the YAEC's program as defined in the Operational Quality Assurance Manua .The Operational Quality Assurance Manual, YOQAP-1-A was approved by NRC letter dated August 3, 1988. There are three groups in the QA section with responsibilities as follows:
Quality Services Group The Quality Services Group provides QA/QC services to the plants. These services include plant surveillance, NDE training and certification, inspections, inspection agency interface, corrective action verification, nonconformance report reviews, and staff training coordination. The QA/QC
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personnel located at the plants report to the Quality Services Group thus maintaining the required independence and providing flexibility of having experience personnel that can be transferred from one plant to another as the workload change Vendor QA Group The Vendor QA group is responsible for maintaining the approved vendor
' list, performing vendor surveillance, auditing vendors, performing design change and procurement reviews,.and reviewing vendor nonconformance report Audit Group The audit group is responsible for the development of the QA program, inplant audits, YNSD audits, technical procedure reviews, preparation of QA procedures, and NRC commitment tracking. The inspectors reviewed an
. internal audit of the Vermont Yankee Project and additional audits of the Vermont Yankee plant were reviewed. These audits included radiation protection, local leak rate testing, housekeeping, fire protection, and Technical Specifications. The audits were found to be thorough, and included significant attributes. The audit findings reflected meaningful concern A review of the May 22, 1989, Plant Audit Discrepancy Status Report indicated that two of thirteen findings listed were overdue for corrective actio In the case of the two overdue items both were observations that did not indicate program deficiencie .0 Plant Engineering Organization The Plant Engineering section reports to the Vice President and Manager of Operations and has three sections. The responsibilities of these sections are as follows:
Engineering Services The Engineering Services group is responsible for maintaining the corporate procedures, Engineering Manuals, Engineering Instructions, and Topical Reports for the four operating plants. This includes assuring the b.iannual review of these procedures for inclusion of industry and regulatory require-ments, and the inclusion of user comment i Mechanical Services The Mechanical Services group provides the corporate NDE services including certification of NDE examiners and inspectors. In addition this group provides corporate fire protection engineers, inservice inspection program review and contracted inspection service Engineering support is provided for welding in the form of procedure qualification records. The infrared thermography engineer also reports to this grou _ - _ _ _ _ _ _ _ _ - _ _ -
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Drafting The Drafting group is responsible for servicing the various Projects for new and revised drawings. This group is also responsible for maintaining the drawings at the operating plant .0 Nuclear Engineering Organization The Nuclear Engineering organization reports to a Vice President and YAEC maintains a staff of engineers concerned with the engineering associated with core physics, transient analysis, LOCA analysis, and safety assessmen These engineers are concerned with the four plants and perform their duties as requested by the plan .0 Environmental Engineering The environmental engineers supply services in the areas of radiological engineering, radiation protection, environmental sciences, emergency planning, and environmental laboratories for analytical and dosimetry service .0 Computer Services The computer engineers provide user services, network operations, computer operations, and computer application .0 Material Management and Control The Material Management and Control section reports to tne President of YAEC. This section is responsible for fuel procurement and limited procurement non safety related expendable supplies for the plant .0 Finance and Administration The inspectors reviewed selected background checks to determine that educational qualifications and personal data as reported by the employee was correct. YAEC retained a contractor to provide investigation services for these verifications. Other aspects of the Finance and Administration section were beyond the scope of this inspectio .C YAEC Support of Industry Organizations Participation in industry related groups and societies is encouraged to assure the company is abreast of the latest information. The company compensates employees for attendance at various meetings. The company is ;
well represented on various groups. In 1989 there were 99 YAEC personnel ;
involved in 174 industry organizations. This resulted in a commitment of approximately five man years of effort. Typical organizations include EPRI, IEEE, Owners Groups, NUMARC, SG0G, ASME, and other professional l societies. In addition, the Vermont Yankee plant had 34 individuals in 43 1 organizations representing another man year of effor )
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, Conclusions-YAEC is very active in the various industry,. professional societies and Lowners groups. The commitment of five man years to this effort is very high considering.a total employment of 400 engineer .0 Communications During the performance of Project tasks.the Project engineers work closely with the-plant engineers. This is accomplished by frequent plant visits
, by the Project Manager, Project Engineering Manager and the discipline engineers. During plant operations the discipline engineers spent approxi-
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mately 10% of their time at the plant. During outages these engineers are responsible for the installation of modifications and spend the major portion of-their time at the plant. Management control-is maintained through regularly scheduled project meetings that review the progress of each request in the areas of design change status, open items, schedules and priorities, . licensing updates, and various other effort A post outage Lessons Learned Workshop is held to asses the performance of all parties. This workshop includes engineering, expediting,. construction, and interfaces between project management, design,.use of contracted personnel and improvements in interfaces. In this meeting each cognizant engineer is required to present comments, and recommendations for improvements
.to be. incorporated into the next outage planning. The report of the workshop
'for cycle 20 at Yankee Rowe contained approximately 100 suggestions for improvemen The inspectors determined that communications are well established at 'l levels between YAEC and the plant .0 Vermont Yankee Corporate Functions The inspector interviewed corporate management and staff personnel to determine technical qualifications and responsibilities in the departments of Procurement and Information Systems, Operations Support, and Technical Training. In addition the inspector ir.terviewed the plant manager and members of his staff and YAEC Quality Assurance personne Procurement and Information Systems The inspector interviewed the management personnel concerning the department realignment that is intended to decrease the time required for procurement, consolidate plant purchases, provide engineering supervision for dedication
.of commercial grade items, and coordinate purchasing with YNSD. New pro-cedures have been developed, reviewed and approved for implementation in August 1989. Standard material requirements have been developed for outage requirements to reduce the need for emergency purchase _ _ - _ _ - _ _ - _ _ - - _ _ _ _ _ _ _ _ _ _ _ -
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'A report-describing all' existing contracts and anticipating future needs L . has been de~ v eloped to' provide timely information for planning and to provid more_ effective. inventory contro Corporate' Administrative Computer Systems Presently several computer systems are functioning in the plant and at the corporate office. This section in conjunction with YNSD is investigating
.the consolidation'n of these systems. This area was beyond the scope of-
.this inspectio ' Operation Support The Operations Support organization of the Vermont Yankee Nuclear Corporation p . supports plant ~ operations in maintenance, technical services, and modifica-tions. The Operations Support organization also provides corporate oversight of the Vermont Yankee plan The . inspector interviewed management personnel and reviewed records of.'th'e Operations Support organization and determined that this organization provides the, services described above. The Operations Support organization provides. thel interface between YAEC and the Vermont Yankee plant. The
- monthly oversight report includes plant performance indicators and summaries
.significant activities such as: operations, environmental, engineering and ~
NRC licensing activities. The status of YAEC activities is reported through status meeting held approximately biweekly or more frequently. as an outage approaches. Technical services include safety evaluation . Vermont: Yankee Technical Training Program-The inspector' reviewed the training procedure and interviewed personnel to determine the extent and quality of training provided by the Vermont Yankee Nuclear Power Corporation to the technical staff and managers. The Te'chnical Staff and Managers Training Program consists.of a central technical core training program, position specific codes and standards lessons, and eight subsections of department specific training programs. The training within the programs consists of classroom, simulator, on-the-job (0JT) training, and self' study. The simulator and OJT type instruction are accomplished during department specific trainin .0 Vermont Yankee plant The inspector held discussions with management and maintenance personnel
.to determineLthe adequacy of offsite support from YNSD. In all cases the plant personnel were satisfied with the technical content, timeliness of the support of both the VY and YAEC organizations. Based on interviews with.YAEC, VY Corporate and plant management personnel engineering super-vision of major modifications and interfaces with the plant engineering staff were excellent. The functional assignment of YNSD engineers to the plant contributes significantly to the quality of engineering suppor _ _ _ _ _ _ _ _ _ _ _ _ _ _
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18.0 Yankee Rowe Modification Installation The inspector reviewed the modification design package developed by YNSD and the records developed by the plant during installation of the new 'C'
emergency battery. This battery was installed in two stages. The first stage was the installation and temporary connection of the batteries in a new location adjacent to the diesel generators. The final stage was the permanent connection of the batteries into the emergency system. The inspector noted that the project was well controlled and the documentation reflected the actual installation during both phases. The inspector observed that there was an emergency, battery operated light fixture, wall mounted adjacent to the new installation. The licensee established that this fixture and the installation was seismically qualifie Conclusions:
The design package furnished by YNSD was complete and considered the needs of the plant. Consideration was given to the area in that the emergency light was seismically qualified, and an electric space heater not seismically qualified was moved to a location away from the battery. In addition a fence was placed adjacent to the batteries to prevent them from inadvertent damage when maintenance was preformed on the battery charge .0 Manegement Meetings Licensee management was informed of the scope and purpose of the inspection
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at the beginning of the inspection. The findings of the inspection were discussed with licensee representatives during the course of the inspection and presented to licensee management at the exit interviews (see paragraph 1.0 for attendees).
At no time dering the inspection was written material provided to the licensee by the inspectors. The licensee did not indicate that proprietary information was involved within the scope of this inspectio _ _ - _ _ _ _ - _ _ _ _ -
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ATTACHMENT A DOCUMENTS AND REQUIREMENTS REVIEWED
Document N Revision Title Yankee Atomic Elt-tric Company Audit 89-03 Feb 20, 1989 Radiation Protection Audit 89-6B Feb 21, 1989 Local Leak Rate Testing Audit 89-D9 Feb 9, 1989 Radwaste Audit 89-10 Mar 13, 1989 Housekeeping and Fire Protection l
l Audit 89-15 May, 8, 1989 Technical Specifications Audit VY88-06 Maintenance VYPP-4 3 Service Requests
- VYPP-6 3 Engineering Design Change Requests
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VYPP-7 3 Plant Design Change Requests VYPP-11 3 Personnel Training l
- YPP-4 7 Control of Service Requests l YPP-6 b Engineering Design Change Requests YPP-7 7 Plant Design Change Requests YPP-11 4 Documentation of Personnel Training Memorandum YRP 1')1/89 Results of Cycle 19 Lessons Learned Summary Report Jan 9, 1989 Participation on Industry-Related Committees, Groups, and Societies
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Jun 26, 1989 Vermont Yankee Status Report 1989 Calendar of Training Programs, Nontechnical Inhouse Programs Vermont Yankee Nuclear Power Corporation
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VY-0SD-106 1 Operations Support Department Training l VY-OSD-112 0 Service Request Procedure TSMPD 5 Technical Staff and Managtrs Training Program VYP:317 Aug 7, 1989 Purchase Order Processing Procedure AP-6025 1 Quality Control / Independent Inspection
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