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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N3901999-10-25025 October 1999 Advises That Info Provided in & Affidavit Re Holtec Position Paper WS-115,rev 1,repts HI-87113, Rev 0,HI-87114,rev 0,HI-87102 Rev 0 & HI-87112,rev 0,marked Proprietary,Will Be Withheld from Public Disclosure ML20217L8591999-10-21021 October 1999 Discusses 990921 Request for Approval to Perform Alternative Testing as Part of Vermont Yankee Nuclear Power Station IST Program.Informs That Submittal Reviewed Against ASME Code Section XI Requirements & Forwards Safety Evaluation ML20217M1181999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20217D9711999-10-13013 October 1999 Responds to Request That Information Titled Addl Info Re Cycle Specific SLMCPR for Vermont Yankee Cycle 21 Be Withheld from Public Disclosure.Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20217F1261999-10-12012 October 1999 Forwards Update to Previously Submitted RELAP5 Analytical Assumptions for App R,Re RAI of 961104 BVY-99-130, Provides Clarification of Method for Determining MSIV Maximum & Minimum Pathway at Vermont Yankee Nuclear Power Station1999-10-0808 October 1999 Provides Clarification of Method for Determining MSIV Maximum & Minimum Pathway at Vermont Yankee Nuclear Power Station ML20217C1501999-10-0707 October 1999 Forwards Insp Rept 50-271/99-11 on 990809-27.No Violations Noted.Insp Focused on Effectiveness of Engineering Functions in Providing for Safe Operation of Plant BVY-99-128, Submits Listed Addl Info in Support of 990414 Request for Clarification to SER Confirming Adequacy of Space Cooling for HPCI & RCIC Sys,Re Item II.K.3.24 of NUREG-0737.Copy of NEDE-24955,encl1999-10-0606 October 1999 Submits Listed Addl Info in Support of 990414 Request for Clarification to SER Confirming Adequacy of Space Cooling for HPCI & RCIC Sys,Re Item II.K.3.24 of NUREG-0737.Copy of NEDE-24955,encl ML20212J7891999-10-0404 October 1999 Informs That Licensee 980804,0628,29 & 990921 Responses to GL 98-01, Y2K Readiness of Computer Sys at NPPs Acceptable.Nrc Consider Subj GL to Be Closed for Plant ML20212J6501999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of VYNPS on 990913. No New Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues & Insp Plan Through Mar 2000 Encl ML20216J3531999-09-29029 September 1999 Responds to NRC Re Violations Noted in Insp Rept 50-271/99-12 on 990628-0811.Corrective Actions:Based on RFO 20 Maint Rule Outage Performance Review,Task Was Generated to Clarify & Enhance SD Monitoring Process BVY-99-122, Notifies of Intention to Reinstate Original Version of App F in FSAR & Correct Docket Re Assumption That Electrical Power Sys Are Designed IAW Requirements of GDC-171999-09-28028 September 1999 Notifies of Intention to Reinstate Original Version of App F in FSAR & Correct Docket Re Assumption That Electrical Power Sys Are Designed IAW Requirements of GDC-17 BVY-99-116, 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-99-113, 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-99-121, 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 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 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 ML20216D7321999-07-26026 July 1999 Forwards Insp Rept 50-271/99-05 on 990510-0620.Two Viiolations Being Treated as Noncited Violations 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 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 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 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 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 ML20196G5241999-06-22022 June 1999 Responds to Re Changes to Vermont Yankee Guard Training & Qualification Plan,Rev 8,Errata A.No NRC Approval Is Required.Encl Will Be Withheld from Public Disclosure Per 10CFR73.21 BVY-99-084, Forwards Proprietary Application & Medical Certificate for Mod of Listed SRO License,For Gj Leclair.Gj Leclair Will Be Trained & Evaluated in Accordance with Util Lsro Training Description.Proprietary Info Withheld,Per 10CFR2.7901999-06-18018 June 1999 Forwards Proprietary Application & Medical Certificate for Mod of Listed SRO License,For Gj Leclair.Gj Leclair Will Be Trained & Evaluated in Accordance with Util Lsro Training Description.Proprietary Info Withheld,Per 10CFR2.790 ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20195H1741999-06-15015 June 1999 Forwards Original & Copy of Request for Approval of Certain Indirect & Direct Transfer of License & Ownership Interests of Montaup Electric Co (Montaup) with Respect to Nuclear Facilities Described as Listed 1999-09-30
[Table view] Category:NRC TO 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 ML20058F2601990-10-31031 October 1990 Forwards Ref Matl Requirements for Reactor Operator Licensing Exams Scheduled for Wk of 910211 ML20058E0791990-10-26026 October 1990 Advises That NRC Will Perform fitness-for-duty Program Insp. Util Written Policies & Procedures Requested ML20058D2651990-10-23023 October 1990 Forwards Insp Rept 50-271/90-80 on 900806-17 & 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 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 ML20059N1351990-09-28028 September 1990 Forwards Safety Insp Rept 50-271/90-09 on 900703-0812 & Notice of Violation 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 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 ML20056A9311990-08-0202 August 1990 Forwards Safety Insp Rept 50-271/90-08 on 900716-20.No Violations Noted ML20056A4021990-07-25025 July 1990 Forwards Radiological Controls Insp Rept 50-271/90-06 on 900618-22 & Notice of Violation 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 ML20059M8731990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C6071990-05-21021 May 1990 Advises That Util 900427 Response to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Box Bow Confirmed That Util Does Not Presently Use Channel Boxes in-core for Longer than One Bundle Lifetime.Action Complete ML20248E0751989-09-26026 September 1989 Forwards Amend 11 to Indemnity Agreement B-49,reflecting Changes to 10CFR140,effective 890701,which Increase Primary Layer of Nuclear Energy Liability Insurance ML20248A3851989-09-25025 September 1989 Forwards Safety Insp Rept 50-271/89-12 on 890718-0905.No Violations Noted IR 05000271/19890801989-09-25025 September 1989 Ack Receipt of Informing NRC of Steps to Correct Violations Noted in Insp Rept 50-271/89-80 IR 05000271/19890131989-09-22022 September 1989 Forwards Safety Insp Rept 50-271/89-13 on 890807-11 & 0828-0901.No Violations Noted ML20247M8651989-09-19019 September 1989 Forwards Safety Insp Rept 50-271/89-14 on 890807-11. Corrective Actions for Six Violations & Two of Three Open Items Found Acceptable & Items Closed.Resolution for Thomas & Betts Connector Qualified Life Inadequate ML20247N0861989-09-15015 September 1989 Forwards Safety Insp Rept 50-271/89-15 on 890821-25.No Violations Noted ML20247N2441989-09-14014 September 1989 Forwards Safety Insp Rept 50-271/89-11 on 890822-24.No Violations Noted ML20246P2501989-09-0101 September 1989 Forwards Technical Evaluation Rept Concluding That Rev 4 to ODCM Uses Methodology Consistent W/Nrc Guidelines & Acceptable Interim Ref.Requests That Points Raised in Conclusions Section Be Addressed within 6 Months IR 05000029/19890141989-08-31031 August 1989 Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted ML20246Q0121989-08-31031 August 1989 Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted ML20246P3671989-08-30030 August 1989 Approves Procedures for Disposal of Slightly Contaminated Septic Waste Onsite,Per 10CFR20.302(a).Disposal Involves Exposure Pathways Less Significant than Pathways Considered in Fes.Procedures Should Be Incorporated in ODCM ML20246K6371989-08-23023 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violation Noted in Insp Rept 50-271/89-80 ML20246D7591989-08-21021 August 1989 Forwards SER Accepting Util Responses to Generic Ltr 83-28, Item 2.2.1, Required Actions Based on Generic Implications of Salem ATWS Events ML20246E7981989-08-21021 August 1989 Advises That Violation Re Testing of CO2 Sys Noted in Insp Rept 50-271/89-04 Still Valid Due to No Alternate to Testing Established,Per Util Requesting Withdrawal of Violation ML20246G2211989-08-18018 August 1989 Clarifies NRC Position Re Definition of Extremity for Purposes of Setting Occupational Exposure Limits,Per NRC Info Notice 81-26.Util Should Ensure That Procedures Incorporate Applicable Dose Limits in 10CFR20 ML20246B7791989-08-11011 August 1989 Confirms 890808 Telcon Re Util Participation in NRC Regulatory Impact Survey on 891025.Feedback from Licensee Will Be Evaluated to Determine Changes to Be Made to NRC Regulatory Approach to Enhancing Safe Operation of Plants ML20248E0131989-08-0101 August 1989 Forwards Safety Insp Rept 50-271/89-09 on 890531-0717. Results Discussed in Rept ML20247N5051989-07-25025 July 1989 Forwards FEMA Rept of 871202-03 Exercise of Offsite Radiological Emergency Preparedness Plans.State of Offsite Emergency Preparedness Not Adequate to Assure Protection of Public Health & Safety ML20245G1321989-07-21021 July 1989 Requests That Encl Ref Matl Be Furnished to NRC by 890821 for Senior Reactor Operator Licensing Exams Scheduled for Wk of 891023.Item 19 of Encl 1 Re Requalification Program Should Be Submitted by 890906 for Wk of 891106 Evaluation ML20246N1331989-07-12012 July 1989 Forwards Safeguards Insp Rept 50-271/89-08 on 890515-19 & Notice of Violation ML20246L2691989-07-10010 July 1989 Documents Results of Meeting 89-074 W/Util on 890510 in King of Prussia,Pa Re Various Operator Licensing Topics, Including Training Program Status,Related Mods & Requalification Program/Exam ML20246B1371989-06-22022 June 1989 Forwards TE Murley Acknowledging Receipt of Ecology Ctr of Southern CA Petition,For Info ML20245A6081989-06-15015 June 1989 Forwards Safety Insp Rept 50-271/89-07 on 890418-0530.No Violations Noted ML20244D0251989-06-0707 June 1989 Forwards Safety Evaluation Accepting Util Second 10-yr Interval Inservice Insp Program Plan.Relief Granted to Requirements That License Determined to Be Impractical to Perform at Facility ML20244B4521989-06-0202 June 1989 Forwards Maint Team Insp Rept 50-271/89-80 on 890227-0310 & Notice of Violation.Written Response Addressing Unresolved Item Re Drywell Paint Peeling Requested within 30 Days IR 05000271/19890051989-05-31031 May 1989 Notifies of Error Identified in Insp Rept 50-271/89-05 Transmitted on 890504.No Deficiencies Identified in Licensee Implementation of Design Change to Comply W/ 10CFR50.62 Should Have Been Stated in Results Section ML20247M0281989-05-26026 May 1989 Forwards Directors Decision,Ltr of Transmittal & Fr Notice in Response to Ocre Petition Expressing Concerns Re 880309 Power Oscillation Event.Petitioner Request Under 10CFR2.206 Denied.W/O Encls ML20247M8981989-05-24024 May 1989 Forwards Request for Addl Info Re 880727 Response to Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. Response Should Be Sent to Viking Sys,Intl at Listed Address ML20247H9991989-05-24024 May 1989 Forwards Second Request for Addl Info Re Use of Frosstey Computer Code for LOCA Analysis.Response Requested within 45 Days of Receipt of Ltr ML20247C6601989-05-19019 May 1989 Informs That Util Response to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Fulfills Requirement ML20247K0841989-05-18018 May 1989 Forwards Safety Insp Rept 50-271/89-04 on 890320-23 & Notice of Violation ML20246L9191989-05-0505 May 1989 Forwards Resident Safety Insp Rept 50-271/89-02 on 890214-0417.No Violations Noted.Programmatic/Performance Weaknesses Noted Re Implementation of Corrective Actions for Deficiencies ML20246H3211989-05-0404 May 1989 Forwards Safety Insp Rept 50-271/89-05 on 890404-07.No Violations Noted 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 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 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 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 ML20207M7771999-03-12012 March 1999 Ack Receipt of Inputs & Comments Re Vermont Yankee Nuclear Power Plant,Provided by Electronic Mail on 990218 & 23 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 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 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 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 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 DD-98-13, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Directors Decision DD-98-13 Has Expired.Decision Became Final Agency Action on 990104. with Certificate of Svc.Served on 9901061999-01-0606 January 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Directors Decision DD-98-13 Has Expired.Decision Became Final Agency Action on 990104. with Certificate of Svc.Served on 990106 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] |
Text
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Docket No.: 50-271
^'w Mr. R. W. Capstick
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Licensing Engineer
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Vennont Yankee Nuclear Power Corporation 1617 W( tester Road i
Framingham, Massachusetts 01701
Dear Mr. Capstick:
Subject:
Control Room Habitability Survey During November 7 and 8,1985, representatives from the NRC staff and our contractor, Argonne National Laboratory, surveyed the Vermont Yankee con-trol room with respect to control room habitability. The survey was part of an industry sampling of several plants, and in the near future will be included in a formal report which will be used in considering further regulatory activities.
For your information we have enclosed a report of our survey. No action is required of you at this time.
Sincerely Vernoh Rooney, Project Manager Project Directorate T-3 Division of Reactor Projects I/II
Enclosure:
As stated cc: See next page DISTRIBUTION:
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r, Docket No.: 50-271 Mr. R. W. Capstick Licensing Engineer Vermont Yankee Nuclear Power Corporation 1617 Worcester Road Framingham, Massachusetts 01701
Dear Mr. Capstick:
Subject:
Control Room Habitability Survey During November 7 and 8,1985, representatives from the NRC staff and our contractor, Argonne National Laboratory, surveyed the Vemont Yankee con-trol room with respect to control room habitability. The survey was part of an industry sampling of several plants, and in the near future will be included in a fomal report which will be used in considering further regulatory activities.
For your information we have enclosed a report of our survey. No action is required of you at this time.
Sincerely Vernoh Rooney, Project Manager Project Directorate I-3 Division of Reactor Projects I/II
Enclosure:
As stated cc: See next page DISTRIBUTION:
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Mr. R. W. Capstick Vermont Yankee Nuclear Power Corporation Yemrmont Yankee Nuclear Power Station cc:
Mr. W. G. Weigand W. P. Murphy, Vice President President & Chief Executive Officer and Manager of Operations Vermont Yankee Nuclear Power Corp.
Vermont Yankee Nuclear Power Corp.
R.D. 5, Box 169 R.D. 5, Box 169 Ferry Road Ferry Road Brattleboro, Vermont 05301 Brattleboro, Vermont 05301 Mr. Donald Hunter, Vice President Mr. Gerald Tarrant, Commissioner Vermont Yankee Nuclear Power Corp.
Vermont Department of Public Service 1671 Worcester Road 120 State Street Framingham, Massachusetts 01701 Montpelier, Vermont 05602 New England Coalition on Nuclear Public Service Board Pollution State of Vermont Hill and Dale Farm 120 State Street R.D. 2, Box 223 Montpelier, Vermont 05602 Putney, Vermont 05346 Mr. Walter Zaluzny Vermont Yankee Decommissioning Chairman, Board of Selectman Alliance Post Office Box 116 Box 53 Vernon, Vermont 05354 Montpelier. Vermont 05602-0053 J. P. Pelletier, Plant Manager Resident Inspector Vermont Yankee Nuclear Power Corp.
U.S. Nuclear Regulatory Commission Post Office Box 157 Post Office Box 176 Vernon, Vermont 05354 Vernon, Vermont 05354 Raymond N. McCandless Vermont Public Interest Research Vermont Division of Occupational Group, Inc.
and Radiological Health 43 State Street Administration Building Montpelier, Vermont 05602 10 Baldwin Street Montpelier, Vermont 05602 Acting Regional Administrator Region I Office Honorable John J. Easton U.S. Nuclear Regulatory Commission Attorney General 631 Park Avenue State of Vermont King of Prussia, Pennsylvania 19406 109 State Street Montpelier, Vermont 05602 Mr. R. W. Capstick Vermont Yankee Nuclear John A. Ritscher, Esquire Power Corporation Ropes & Gray 1671 Worcester Road 225 Franklin Street Framingham, Massachusetts 01701 Boston, Massachusetts 02110 t
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I VISIT TO VERMONT YANKEE i
System Description and Operation On November 7 and 8,1985, representatives from Region I, NRR and Argonne National Laboratory surveyed the Vermont Yankee control room. The control room is designed.to take 3700 cfm of outside air and 8800 cfm of recirculated control room air, pass it through a prefilter, c. hiller, and heater prior to discharging a portion of it back into the control room. Of this air flow of 12,500 cfm of air, 3400 cfm is sent to the cable vault. The III.D.3.4 submittal had indicated the 3400 cfm first went to the computer room and then to the cable vault. However, the ventilation system has been modified such that only 200 cfm of control roon intake air is supplied to the computer room.
l The computer room is cooled by a separate cooling unit which provides no additio'nal ventilation air. The remaining flow (3200 cfm) is sent to the cable vault. A total of 300 cfm is exhausted by control room toilet and the control room kitchen fans.
During a toxic gas incident, the supply / recirculation fans for the control room continue to operate but the intake, which has a circular damper shaped like a satellite dish, is isolated. The exhaust fans from the toilet and kitchen are automatically shut off. The control room is pressurized to 1/8" W. G. through the use of bottled air with a halon type discharge. A total d
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3 of 106 ft of air is discharged into the control room at a pressure of 440 psi in a period of 20 seconds. Another four bottles of air gradually discharge j
their contents, also at 440 psi to bring the control room to a positive pressure of 1/8" W. G in a period of 4 minutes. Operators are expected to have donned their bio-packs within this period of time.
The only mechanism for isolating the control room is with a toxic gas signal.
Placing the system in recirculation does not shut off the toilet and kitchen exhaust fans. This was demonstrated when the control room operator placed the system in recirculation.
Plant personnel did not seem to be aware that the radiological analysis of III.D.3.4 had assured the control room isolated so that that the only source 4
of activity was an inleakage of 20 cfm which the licensee indicated was verified by a SF test. Plant personnel presumed that the exhaust fans could 6
continue to operate during such an incident.
A check of operating procedures also confirmed this. The operation of such fans made the control room extremely negative in terms of pressure.
This was evidenced when the fans were turned off after recirculation was ended. The blades of the kitchen and toilet exhaust fans quickly reversed their direction.
1 The control room appeared to be neutral when operating in the nomal makeup.
mode. Measurements of flow were not taken at the exhaust dampers and at the I
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. discharge to the computer room and to the cable vault.
It is possible that the significant negative pressure seen by the control room during recirculation may occur as a result of pulling air from these two general areas.
The intake damper seemed to seal very tightly. The cognizant engineer at Vermont Yankee indicated that this damper had replaced a louvered damper.
Leakage seemed minimal during recirculation.
Control Room Temperature Control room temperatures seemed to be constant throughout the control room envelope. When the system was placed in recirculation the control room
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temperature increased from 71*F to 74*F in about 20 minutes. One shift supervisor indicated that this was not unusual and that temperatures had reached 90'F in the control room. Another indicated that they often placeo the system in recirculation during the winter to provide some additional heat to the control room. One individual indicated that the chillers are continuously maintained but do not begin operation until reaching 74*F.
The controi room equipment qualification temperature has not been determined.
There are no technical specifications addressing temperature limitations in the control room.
System Integrity and III.D.3.4 Analysis The radiological dose evaluation consisted of 2 sources. One was MSIV leakage and the other was the filtration of various leakage by the equivalent of a I
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standby gas treatment system (SGTS) and subsequent release from the stack.
Their respective contribution to the thyroid dose was 18.8 and 8 rem. Vermont Yankee did not add these two values together because they maintained that the control room operator could only receive one or the other due to meteorological conditions. This is most probably true.
It was difficult to assess the SF experiment in the control room. Since a 6
portion of the total 20 cfm inleakage was attributed to ingress and egress of the control room, the acceptance criteria should have been somewhat less than 20 cfm. The data reported to Vennont Yankee seemed to indicate that during a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period of the test, there was a decrease in SF concentration while a 6
concentration. This could not similar 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period showed an increase in SF6
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be explained by the cognizant engineer.
The control room at Yermont Yankee and its ductwork appeared to be very tight. A considerable amount of time had been spent to ensure this.
Vermont Yankee utilizes Beckman instrumentation to monitor for toxic gases.
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They originally experienced some problems with radio frequency interference causing the CL detectors to spike. Water sometimes masked the reference cell 2
for the CO m nitor but a periodic N2 purge has corrected this problem. The 2
methanol detector experienced a problem with its dry cell power supply. A recent technical specification submittal addressing toxic gases has been rejected by the NRC.
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D The control room intake does not have a radiation monitor nor does it have an area radiation monitor.
Conclusion Based upon the survey, Vermont Yankee should have technical specifications on the control room which:
(1) Demonstrate that the control room isolates on a toxic gas incident and a radiological incident.
(2) Demonstrate that control room envelope is maintained so that in
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leakage is no greater than 20 cfm.
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(3) Limit equipment temperatures.
Similar to other facilities surveyed, there seems to be a breakdown in the transfer of information from those doing the safety evaluation to those implementing the safety evaluations assumptions through operations and procedures.
Radiation monitors should be added to the control room intake and to the control room area.
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Vermont Yanke t Nuclear Station Page i PLANT VISIT
SUMMARY
REPORT 1.
Plant:
Vermont Yankee Nuclear Station 2.
Utility:
Vermont-1 Yankee Nuclear Power Corp.
3.
Location:
Vernon. Vermont 4
NRC Region:
I S.
Visit Date:
November 7-8, 1985 6.
Participants from Argonne National Laboratory:
J. W. Driscoll R. J. McConnell 7.
Scope:
The plant visit was made to gather information on control room j
habitability - Generic Issue 83.
Specifically the safety analycis (including III.D.3.4. submittal and the Nac starr safety evalua-(.
tion) and plant procedures were reviewed to determine what cpora-tional practices are being employed.
Air flow and temperature measurements were taken in various places throughout the CR HVAC system and envelope.
8.
Findings:
8.1 Procedures I
8.1.1 Ceneral In preparation for the review. several maintenance and operating procedures were reviewed. The proce-dures were remarkably clear as to the purpose and method to be employed and in general the best we have reviewed to date.
8.1.2 Findings (1) The procedures did not require an automatic or manual isolation of the normal air intake after a high radiation alara.
(2) Alars response and calibration procedures t
indicated different trip setpoints for the initiation of the automatic isolation of the toxic gas isolation system on a high Cle signal. The design analysis indicated a third value based on time required to put the system I
in the isolated mode of operation.
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Vermont Yankee Nuclear Station Page 2 (3) The safety analysis performed by Yankee Atomics involvin6 the radiation dose to the control room operator was based on the control room being isolated. The intent of the safety analysis was not included in plant proce-dures.
It is recommended that a member of the safety analysis group be included or the Proce-dures Review Committee for the review of proce-dures related to safeguards system.
8.2 Technical Specifications 8.2.1 Ceneral There is no existing Technical Specification for the Control Room HVAC System at Vermont Yankee..The review team was informed that a Technical Specifica-tion is being prepared to cover the Toxic Gas Isola-tion System and the Emergency Breathing Air System.
8.2.2 Findings
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The following items should be considered for inclu-sion as Technical Specification items:
(1)
The basis for the control room operator dose uses standard evaluation methods and assumptions are in general agreement with other plants reviewed.
The key item among the assumptions is that the unfil-tered infiltration rate is 20 CFM for the duration of the accident.
Since the safety analysis assumed a 20 CFM infiltestion rate, the Technical Spacificit!<.:
snould require the same automatic isolation on a high ractation as is provided by a high toxic gas signal. This would require the addition of a radiation detector (s) at the outside air inlet and control circuitry to place the con-trol room HVAC system in the recirculation mode. See discussion in Section 8.4. Outside Air Infiltration.
(2)
The equipment, e.g., bottled air, toxic gas monitors, radiation monitors, needed during a toxic gas release or radiation accident should be evaluated and this equipment should be specified in the Technical Specifications.
(3) A limit for maximum temperature in the control room envelope should be included in the Tech-i nical Specifications. An assessment of the f
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instrument rating should be made and a limit established where instrumentation will not be adversely affected.
(4)
A test should be run periodically to verify the leaktightness of the control room envelope.
This could be accomplished by pressurizing the control room emergency breathing air bottles and observing that control room envelope pressure was maintained at 1/8-in. WG for four minutes (design criteria of emergency air breathing system based on a 20 CFM inleakage).
or by using a small fan to pressurize the control room through the toilet and kitchen exhaust fan penetration on an alternating bases.
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(5)
Response time limits should be established for the time from sensing a toxic gas to the actual closure of inclation valves.
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(6)
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The minimum pressure required on the emergency breathing air banks snould be included in the Technical Specifications.
8.3 HVAC Flow and CRE Temperature Measurements 83.1 Ceneral The control room HVAC system is a very tight system and there are very few places provided to obtain air flow measurements.
During normal operation.
3700 CFM of unfiltered cutside air is mixed with the control room return air (about SS00 CFtt).
The intake structure for the control room HVAC system is shared with another system.
8 3.2 Findings (1)
Readings were taken at the intake structure with the control room and administration build-ing HVAC systems in normal operation and with the control room system in the rectroulation (Administration Building HVAC system mode.
remains in normal operation.) The difference of the two readings indicated that 3700 CFM fresh air makeup to the control room HVAC system is accurate.
(2)
Measurements using a smoke gun indicated that 4
the control room was at a neutral pressure with J
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Vermont Yankee Nuclear Station Pacc 4 respect to adjacent areas when the system was in the normal supply mode and that the control room is at a negative pressure with respect to adjacent areas when in the emergency isolation mode.
(3) Normal flow through the kitchen and toilet exhaust fan was measured to be about 150 CFM Flow measurements were not taken in the each.
Emergency Isolation mode.
(4)
When the system is in the Emergency mode, the Kitchen and Exhaust Fans continue to run and their respective isolation dampers remain open.
(5)
Temperature measurements throughout the control room envelope indicated an even temperature in all areas. The maximum variation was about 3*F.
(6)
When the 00ntr01 room was isciated in the
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emergency ~.0c9 the temperature of the cettrol s
g' room general arca rese about 5'F in 20-30 minutes.
(7)
Measurements were not taken with the system operating in the Toxic Gas Isolation mode.
(8)
Flow readings were not taken in the supply line of the cable valut and battery rooms due to inaccessibility to ducting.
Flow reading in this line in the Emergency Isolation Mode may have some bearing on the control room negative pressure durine syntet is0lation.
t 8.4 Outside Air Infiltration i
i 8.4.1 General The Vermont Yankee control room system is very tights we believe this is the tightest control room envelope that we have seen to date.
In 1982 an SF.
air dilution test was run to confirm the leaktight-ness of the control room envelope. The data that was obtained is somewhat inconclusive since the system was not placed in the emergency mode but in what is now called the toxic gas isolation mode, which closed the fresh air inlet isolation valve, the supply to the computer and cable vault isolation valve, and the kitchen and toilet fans were stopped e
l with their respective isolation valves closed.
The SFs test indicated in this condition the control l
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room has little or no inleakage. However, if the system is placed in the emergency mode using a switch in the control room the kitchen and toilet exhaust fans are not secured and their respective isolation dampers remain open. Furthermore, we are not convinced that the SF. test data is conclusive for the low inleakage found in the Vermont Yanvae control room.
It was also not evident that the control room temperature was considered as having any affect on the SF concentrations during the course of the test (see Item 8.5.2).
8.4.2 Findines Since the safety analysis assumed a 20 CFM infil-tration rate based upon the control room being isolated, the review team wanted to know what caused 3
isolation of the control room and how quickly the outside air makeup was stopped.
The following observations were made:
1 A review of plant drawings and the FSAR indicated that no automatic action occurred.
2.
A review of plant procedures did not indicate any operator action was required.
3.
On discussing items 1. and 2. above with the plant staff, the plant staff seemed to be under the impression that it was not necessary, under an accident condition, to secure the fresh air makeup because the radiation challenge was below the linits set forth in General Design Criterion 19.
The plant staff did, however, point out that fresh air makeup could easily be shut off by placing a control switch for the control room HVAC system, located in the control room, in the emergency position. The review team requested that this be done. The result of shutting off make up air was that the control room envelope went from a neutral pres-sure to a negative pressure with respect to the surrounding areas.
The negative pressure was apparently created due to the continued operation of the kitchen and toilet exhaust fans while in the emergency recirculation mode of opergtion.
It was apparent to the review team that under the negative pressure conditions, infiltration r;
would certainly exceed the 20 CFM assumption.
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Concern by the review team about how the control room operators would spat down the exhaust fans and dampers indicate that a con-venient method is not available within the control room.
The conclusion, on air infiltration, by the review team is:
Adequate procedures and or controls are not avail-able to ensure that the safety analysis assumption (20 CFM unfiltered inleakage) can be met.
B.5 LER Evaluation 8.5.1 ceneral Since there is no Technical Specification applicable to the control room HVAC system, LER's have not been written concerning loss of cooling to the control room envelope.
8.5.2 Findings
,fs When the systo:a was placed in the emergency recircu-lation mode. 1 noticeable increase in control room ambient temperature in a short period of time was observed by the review team (see Itse 8.3.2(6)3.
Discussion with the shift supervisor indicated that the temperature has risen to above 90*F with the system in the emergency mode for about two hours.
An evaluation should be made to determine that the cooling equipment operates to provide cooling in both normal and emergency modes of operation.
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