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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N3901999-10-25025 October 1999 Advises That Info Provided in & Affidavit Re Holtec Position Paper WS-115,rev 1,repts HI-87113, Rev 0,HI-87114,rev 0,HI-87102 Rev 0 & HI-87112,rev 0,marked Proprietary,Will Be Withheld from Public Disclosure ML20217L8591999-10-21021 October 1999 Discusses 990921 Request for Approval to Perform Alternative Testing as Part of Vermont Yankee Nuclear Power Station IST Program.Informs That Submittal Reviewed Against ASME Code Section XI Requirements & Forwards Safety Evaluation ML20217M1181999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20217D9711999-10-13013 October 1999 Responds to Request That Information Titled Addl Info Re Cycle Specific SLMCPR for Vermont Yankee Cycle 21 Be Withheld from Public Disclosure.Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20217F1261999-10-12012 October 1999 Forwards Update to Previously Submitted RELAP5 Analytical Assumptions for App R,Re RAI of 961104 BVY-99-130, Provides Clarification of Method for Determining MSIV Maximum & Minimum Pathway at Vermont Yankee Nuclear Power Station1999-10-0808 October 1999 Provides Clarification of Method for Determining MSIV Maximum & Minimum Pathway at Vermont Yankee Nuclear Power Station ML20217C1501999-10-0707 October 1999 Forwards Insp Rept 50-271/99-11 on 990809-27.No Violations Noted.Insp Focused on Effectiveness of Engineering Functions in Providing for Safe Operation of Plant BVY-99-128, Submits Listed Addl Info in Support of 990414 Request for Clarification to SER Confirming Adequacy of Space Cooling for HPCI & RCIC Sys,Re Item II.K.3.24 of NUREG-0737.Copy of NEDE-24955,encl1999-10-0606 October 1999 Submits Listed Addl Info in Support of 990414 Request for Clarification to SER Confirming Adequacy of Space Cooling for HPCI & RCIC Sys,Re Item II.K.3.24 of NUREG-0737.Copy of NEDE-24955,encl ML20212J7891999-10-0404 October 1999 Informs That Licensee 980804,0628,29 & 990921 Responses to GL 98-01, Y2K Readiness of Computer Sys at NPPs Acceptable.Nrc Consider Subj GL to Be Closed for Plant ML20212J6501999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of VYNPS on 990913. No New Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues & Insp Plan Through Mar 2000 Encl ML20216J3531999-09-29029 September 1999 Responds to NRC Re Violations Noted in Insp Rept 50-271/99-12 on 990628-0811.Corrective Actions:Based on RFO 20 Maint Rule Outage Performance Review,Task Was Generated to Clarify & Enhance SD Monitoring Process BVY-99-122, Notifies of Intention to Reinstate Original Version of App F in FSAR & Correct Docket Re Assumption That Electrical Power Sys Are Designed IAW Requirements of GDC-171999-09-28028 September 1999 Notifies of Intention to Reinstate Original Version of App F in FSAR & Correct Docket Re Assumption That Electrical Power Sys Are Designed IAW Requirements of GDC-17 BVY-99-114, Provides Notification That Licensee Completed Y2K Remediation Efforts Described in Util 990608 Response to NRC GL 98-01,Suppl 11999-09-21021 September 1999 Provides Notification That Licensee Completed Y2K Remediation Efforts Described in Util 990608 Response to NRC GL 98-01,Suppl 1 BVY-99-113, Requests Approval to Perform Alternative Testing to That Specified by ASME Boiler & Pressure Vessel Code,Section XI & Asme/Ansi OM, Operation & Maint of Nuclear Power Plants. Attachment 1 Provides Justification for Alternative Testing1999-09-21021 September 1999 Requests Approval to Perform Alternative Testing to That Specified by ASME Boiler & Pressure Vessel Code,Section XI & Asme/Ansi OM, Operation & Maint of Nuclear Power Plants. Attachment 1 Provides Justification for Alternative Testing BVY-99-116, Informs of Determination That Wh Schulze,License SOP-10528-1,will No Longer Maintain License at Facility. Termination of License Requested1999-09-21021 September 1999 Informs of Determination That Wh Schulze,License SOP-10528-1,will No Longer Maintain License at Facility. Termination of License Requested BVY-99-121, Requests Extension Until 990929 to Respond to Violations Noted in Insp Rept 50-271/99-12,dtd 990819.Licensee Did Not Receive Rept Until 990830 & Addl Time Is Needed to Prepare & Allow for Adequate Review of Violation Response Submittal1999-09-20020 September 1999 Requests Extension Until 990929 to Respond to Violations Noted in Insp Rept 50-271/99-12,dtd 990819.Licensee Did Not Receive Rept Until 990830 & Addl Time Is Needed to Prepare & Allow for Adequate Review of Violation Response Submittal ML20212C1621999-09-17017 September 1999 Forwards Amend 175 to License DPR-28 & Safety Evaluation. Amend Revises TSs to Enhance Limiting Conditions for Operation & Surveillance Requirements Relating to Standby Liquid Control System BVY-99-118, Responds to RAI Concerning GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions1999-09-16016 September 1999 Responds to RAI Concerning GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions BVY-99-115, Forwards non-proprietary & Proprietary Responses to 990714 RAI Re Civil & Mechanical Engineering Considerations for Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355.Proprietary Encls Withheld1999-09-16016 September 1999 Forwards non-proprietary & Proprietary Responses to 990714 RAI Re Civil & Mechanical Engineering Considerations for Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355.Proprietary Encls Withheld ML20216F3171999-09-13013 September 1999 Forwards Insp Rept 50-271/99-06 on 990621-0801.One Violation Identified & Being Treated as Noncited Violation BVY-99-111, 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 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 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 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 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-99-103, Informs That Util Expects to Submit Approx Twenty Licensing Actions in FY00 & FY01,in Response to Administrative Ltr 99-021999-08-18018 August 1999 Informs That Util Expects to Submit Approx Twenty Licensing Actions in FY00 & FY01,in Response to Administrative Ltr 99-02 BVY-99-100, Forwards Revised Floor Response Spectra Diagrams,Originally Sent as Attachment 1 to Licensee to Nrc.Revised Diagrams Have More Legible Scale Markings1999-08-0202 August 1999 Forwards Revised Floor Response Spectra Diagrams,Originally Sent as Attachment 1 to Licensee to Nrc.Revised Diagrams Have More Legible Scale Markings ML20210M5791999-07-30030 July 1999 Responds to NRC 990726 Telcon Re Status of Resolution for USI A-46 Outliers.Written Summary,By Equipment Category, Listed ML20211E1701999-07-28028 July 1999 Forwards Copy of Final Exercise Rept for 990427-29,full- Participation Plume Exposure & Ingestion Pathway Exercise of Offsite Radiological Emergency Response Plans site-specific to VYNPS ML20210G5041999-07-27027 July 1999 Responds to NRC 990301 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions. Licensee Will Submit Info Re Proposed Sys Mod by 990916 ML20210G4271999-07-27027 July 1999 Forwards Testing Data & Associated Results for Fitness for Duty Program at Plant for 990101-0630 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 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 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 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 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 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 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
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Text
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Jcnu:ry 5, 1987 Docket No. 50-271 Mr. R. W. Capstick Licensing Engineer Vermont Yankee Nuclear Power Corporation 1671 Worcester Road Framingham, Massachusetts 01701
Dear Mr. Capstick:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - IST PROGRAM Re: Vermont Yankee Nuclear Power Station We are reviewing your proposed Inservice Testing (IST) program for pumps and valve testing which you submitted by letter dated November 27, 1984. We find that we need additional information as described in the enclosed questions, to complete our review. We believe that this information could most efficiently be communicated in a meeting between your representatives and our reviewers in -
Region I.
I request that you contact me and propose a date for such a meeting.
The reporting and/or record keeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
l Sincerely, Qr'-S-f C9+1 by Vernon L. Rooney, Project Manager BWR Project Directorate #2 Division of BWR Licensing
Enclosure:
As stated cc w/ enclosure:
See next page D' S"RLB JTION
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DBL:PD#2 DBL:PD#2 /d DBWP!fvI SN M VRooney:cb DM611er
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Kr. R. W. Capstick Vermont Yankee Nuclear Power Vermont u nkee Nuclear Power Corporation Station cc:
Mr. J. G. Weigand Mr. W. P. Murphy, Vice President &
President & Chief Executive Officer Manager of Operations Vermont Yankee Nuclear Power Corp.
Vermont Yankee Nuclear Power Corp.
R, 9. 5, Box 169 R. D. 5, Box 169 Ferry Road Ferry Road Brattleboro, Vermont 05301 Brattleboro, Vermont 05301 Mr. Dcnald Hunter, Vice President Mr. Gerald Tarrant, Comissioner Vernor t 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 Public Service Board Nuclear Pollution State of Vermont Hill and Dale Farm 120 State Street R. D. 2, Box 223 Montpelier, Vermont 05602 Putney, Vermont 05346 Vermont Yankee Decomissioning Mr. Walter Zaluzny Alliance Chairman, Board of Selectman Box 53 Post Office Box 116 Montpelier, Vermont 05602-0053 Vernon, Vermont 05345 Resident Inspector Mr. J. P. Pelletier, Plant Manager U. S. Nuclear Regulatory Comission Vermont Yankee Nuclear Power Corp.
Post Office Box 176 Post Office Box 157 Vernon, Vermont 05354 Vernon, Vermont 05354 Vermont Public Interest Mr. Raymond N. McCandless Research Group, Inc.
Vermont Division of Occupational 43 State Street
& Radiological Health Montpelier, Vermont 05602 Administration Building 10 Baldwin Street Regional Aoministrator, Region I Montpelier, Vermont 05602 U. S. Nuclear Regulatory Comission 631 Park Avenue i
Honorable John J. Easton King of Prussia, Pennsylvania 19406 Attorney General State of Vermont Mr. D. Caphton, Region I r
109 State Street U.S. Nuclear Regulatory Commission Montpelier, Vermont 05602 631 Park Avenue John A. Ritscher, Esquire Ropes & Gray 225 Franklin Street Ellyn R. Weiss Ij" " 8' [ fe, N.W.
Boston, Massachusetts 02110 4
s Suite 430 f
Washington, DC 20009-1125 i
Request for Additional Information Concerning the Vermont Yankee Inservice Testing (IST) Program for Pumps and Valves
(
Reference:
letter Warren Murphy to NRR dated November 27,1984.)
The following questions have evolved from the initial staff review of the Vermont Yankee IST Program for pumps and valves, i
i l
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-.- --._,, __.._., _--- --.,,,_..... _. -__.. _ -.,--r-
Pumps 1.
Service Water Pumps P7-1A-D G191159 Sh-1 The WP appears to be measurable, however, the program's pump testing does not indicate this. The listing should be revised.
2.
High Pressure Coolent Injection Pumps G-191169 Sh 2 HPCI Gland Seal Exhauster HPCI Hot Well Condensate Pump Discuss the safety related functions (shutting down the reactor or in mitigating the consequences of an accident) of these pumps. Provide a detailed technical justification for not incibding the pumps in the program.
3.
Standby Liquid Control Pumps Is lubricant temperature measured in the pump crankcase or another location?
4.
Core Spray Pumps P46-1A/B During outage testing, is the length of time of the pump run adequate to reasonably assure that no problems are being experienced as a result of bearing heating? Note-this comment is applicable to the other pumps in the program that similarly have bearing temperatures that can not be directly measured.
5.
RCIC Condensate and Vacuum Pumps G191174 Sh. 2 Discuss the safety related functions of these pumps. Provide a detailed technical justification for not including these mps in your program.
6.
RBCCW Pumps G191159 Sh. 3 The program listing for the reference drawing shows sheet 1, the pumps are on sheet 3.
7.
Emergency Diesel Generator Auxiliaries G191162 a.
The diesel engine's fuel pump and clean oil return pumps are missing from the program.
b.
In relief Request Basis P-12. Fuel Oil Transfer Pump Bearing Temperature measurement per IWP-3300, regarding alternate testing, is it possible to check bearing temperatures by pumping to the 5000 gallon Fuel Oil Day Tank 41-1A for the heating boilers?
f
7 2
8.
Pump RRU-18 and G 191175 Sh. 1 a
Two check valves 16-19-101 (E-15) and 16-19-103 What are the safety related functions of the pump and two check valves?
9.
What is the technical justification for not including the Torus to Drywell pumpback system in the IST program? (No drawings provided).
G-191177 Sh. I
- 10. Describe any functions that the Drywell Floor Drain pumps P-11 A/B and the Drywell Equipment Drain pumps P-15-A/B have in shutting down the reactor or mitigating the consequences of an accident.
4 l
4
Valves V-4* Service Water System Dwg. G191559 Sh.1&2 1.
Valve V 70-1A-D and RRB-V1 (B,H-3) a.
The relief request lacks specificity regarding frequency of exercise testing. The time period should be specified.
Reference IWV-3521.
(Note: 24 months is normally the maximum relief that the staff will consider.)
General Note applicable to all relief requests:
Relief request should clearly specify what specific relief is being requested including the detailed technical basis for the specific relief being requested.
Revise relief requests accordingly, b.
Is there a leakage requirement established for these valves in the closed position? Is prompt closure verified?
2.
Relief valves in Service Water System Provide detailed justification for not including the service water system's relief valves in the IST program and testing in accordance with IWV-3510.
3.
RHR Motor Cooling What is the technical bases for not including: check valves 181 XC (4 total, one for each motor) and Solenoid valves SE-70-4C (4 Total)?
4.
Valve V 70-84A and 84 B Reference G191159 Sh. 2) (B and H-3).
What is the safety related function of these valves?
5.
Emergency Diesel Generator Cooling a.
Check Valve 70-1 (B-9)
This check valve is not in the program, however, the position of the valve appears to be of safety related importance to assure a heat sink for the emergency diesels and as such should be tested as a Category C valve.
b.
Fill Valves On Expansion Tanks SE-70-2A? (Drawing has no numbers)
(F-8)
SE-70-2B (C-5)
- The V-numbers used correspond with the VY program numbers.
2 These valves are not in the program, however, appear to have safety importance to assure cooling of the EDGs. The valves should be included in the program and tested.
6.
Line 24" SW IB (Dwg. G191159, Sh.1) appears to connect to 8" SW 18B (Dwg. G151159, Sh. 2) at match line A, however, there is no reducer shown.
Is there a missing drawing? Also there is no 24" SW IB in the " Piping Line List".
Also the 18" SW 12 line goes to 20" SW-12? Same question?
V-5 Reactor Building Closed Cooling Water 1.
Relief Valves G191159Sh.3(A-4)
RBCCW HX's SR 70-1A/B Provide detailed technical justification for excluding these two relief valves from the program.
2.
Air Operated Valve (D-8)
LCV-1 Does this valve operate to make up system losses of inventory? Does the valve fail open upon loss of air?
V-7 Service and Instrument Air, Diesel Generator Starting Air System, Dwg. G-191160 Ref. Sh. 7 1.
Pressure Relief Valves (unnumbered) on EDG Air Receiver Tanks, one on each tank, four total.
(Ref. Sheet 7 of 7)
Provide your detailed technical justification for not including these valves in the IST program and testing per IWV-3510.
2.
Check valve unnumbered in line from air receiver to motor pressure switch, one for each air receiver, (Ref. Sheet 7 of 7).
Provide your detailed technical justification for not including these valves in the IST program and testing per IWV-3510.
3.
Pressure Relief Valves (unnumbered) on air compressors, two total.
Provide your detailed technical justification for not including these valves in the IST program and testing per IWV-3510.
4.
EDG Air Start Solenoid Valves (ColtIndustriesDwg. 1185383)
Provide your detailed technical justification for not including these valves in the IST program and testing per IWV-3400.
3 5.
Valve V72-78 A-D and V72-80 A-D Dwg. G191160 Sh. 7 Do these valves have to meet a leakage criteria to protect against the loss of receiver redundancy?
6.
Relief Request Basis V5 Revise to show compliance with requirements of IWV-3423 regarding adjusting to functional maximum pressure differential value.
7.
Instrument Air System Ref. G191160 Sh. 4 What is the safety function of check valves:
Check valve next to V 72-154 and unnumbered (L-6)
V 72-51A V 72-155 (Check valve is next to and unnumbered)
V 72-86A Y 72-868 Y 72-51B V 72-49A V 72-498 V 72-67A (L-17)
V 72-67B 8.
Relief Request Basis V6 For Valves V72-89 B/C Dwg/ G191160 Sh. 3 (K-12 and 15)
Relief request as written does not show compliance with exercise testing frequency under IWV-3522. Revise to meet Section XI.
Note: The leak test requirement Ref. RRB-V5 needs to be revised to comply with IWV-3426 and IWV-3427, Analysis of Leakage Rates and Corrective Action, respectively.
l 9.
Check Valve V72-103 Dwg. G191160 Sh. 3 What is the basis for specifying the valve to be passive? The valve is categorized as AC, however, the exercise requirements are not specified.
- 10. Check Valves I
What is the safety related function of these valves?
V-72-70 A/B G191160 Sh. 3 L-17 V-72-26 A/B G191160 Sh. 3 L-12 V-72-26 G/H G191160 Sh. 3 L-11 i
V-72-68 A/B G191160 Sh. 3 J-11 V-72-37 A/B 6191160 Sh. 6 L-7)
I
4 V-8 Emergency Diesel Generator Fuel Oil System Dwg. G-191162 1.
Is valve LCV-3 (D-5) required to operate at anytime the EDGs are responding to an accident condition?
2.
Relief Yalves 3A and 3B (C-4)
Provide detailed technical justification for not including these valves in the program and testing per IWV-3510.
3.
Two relief valves and four check valves are shown on the drawing at the EDG.
Provide you detail technical justification for not listing the valves in the program.
4.
Clean Oil Tank (0-10) a.
How is the tank vented?
b.
Are there any check valves installed in the pump discharge piping?
5.
EDG Lube Oil System What are the drawing numbers that show this system? (No drawings were provided.)
V-9 & 10 Nuclear Boiler G191167 1.
Relief Valves SR2-14E-L and RRB V7 (L-11)
Under " Alternate Testing", RRB V7 should also specify exercise testing during refueling outages.
2.
Relief Valves SR2-14 A-D (L-11)
Provide your technical justification for not testing these relief valves.
3.
Valves V2-37A check)
B7 SIA solenoidoperated)
C-8 Provide your detailed technical justification for not including these valves (one set for each relief valve).
5 4.
RRB V 11 For Safety and Relief Valves The VY testing frequency of testing all valves every two refueling outages is more conservative than the Code frequency of testing all valves every five years. However, the relief request does not adequately address the IWV-3513 additional test aspects regarding corrective action to be taken in the event a failed valve is identified. The relief request states that additional testing is unreasonable per IWV 3513, however, provides no bases for handling the failure issue.
Provide your technical bases for handling the valve failure issue and specify alternate requirements.
5.
Feedwater Valves V2-27A F-3 V2-96A H-3 and RRB V8 These valves should comply with the analysis of Leakage Rates and Corrective Action Requirements, Paragraphs IWV-3426 and i
IWV-3427, respectively. The relief request should be revised accordingly.
6.
Feedwater Check Valves V2-28 A/B (F-4)(H-4) and RRB V9 Note: Valves have a safety related function to close as an isolation valve and a safety function to open upon HPCI &
RCIC injections. No relief from quarterly exercise testing was included.
Do you intend to exercise quarterly?
These valves should comply with the analysis of Leakage Rates and Corrective Action Requirements, Paragraphs IWV-3426 and IWV-3427, respectively. The relief request should be revised accordingly.
7.
Process Sampling Valves l
V2-39 L-4)
V2-40 L-3)
RRB-V8 These valves should comply with the analysis of Leakage Rates and Corrective Action Requirements, Paragraphs IWV-3426 and IWV 3427, respectively. The relief request should be revised accordingly.
l I
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6 8.
Steam Drain Valves:
V2-74 D-10 V2-77 D-13 a.
-Provide your detailed technical justification for not exercising and stroke time testi..g these Category A valves.
b.
The valves must comply with the Analysis of Leakage Rates and. Corrective Action Requirements, Paragraphs IWV-3426 and 3427, respectively.
c.
The relief request RRB-V8 needs revising accordingly.
9.
MSIVs V2-80 A-D D,F,G,H-10)
V2-86 A-D D. F, G, H-13) a.
The valves must comply with the Analysis of Leakage Rates and Corrective Action Requirements, Paragraphs IWV-3426 and 3427, respectively. Revise the relief request RRV-V8 accordingly.
10.
Excess Flow Check Valves G191167 SL-23 SL-301F SL-3018 SL-301A SL-301E SL-978 M-12)
Describe the safety related function of each of these check valves.
- 11. MSIV Supply Check Valves IA 87 A-D B-12 CA 87 A-D B-10 Provide detailed technical justification for not including these i
valves in the program.
These valves appear to assure that the MSIV accumulators remain at pressure in the event of a loss of header pressure. They appear to be Category C valves.
l t
7 V-11 Core Spray System Reference Drawing G-191168 SR 20 A and B Safety Relief Valves Provide a detailed technical basis for not including these valves in the program and testir.g per IWV 35107 2.
M0V 12 A and 12 L (Outsidecontainment)
Check Valves V13A and V138 (Iriside containment)
These valves provide the redundant barrier between high and low pressure piping.
Provide detailed technical justification for not designating as Category A and leak testing.
3.
MOV-V7Aand78(CSPumpSuction)
What function (s) do the valves serve to mitigate the consequences of an accident.
(The valves are not in the IST program).
4.
Excess flow check valve SL-25 Why is this valve not tested similarly to SL 31 A&B? (Thevalveis not on relief request RRB-V16).
5.
Check Valves 33A and 338 (CS pressurizing lines)
Do these valves close to mitigate an accident? Discuss their function.
V-12-14 High Pressure Coolant Injection System (HPCI)
G191169, Sh.1 1.
Steam Valves and RRB-V17:
V23-15 E-5 V23-16 E-7 The valves must comply with the Analysis of Leakage Rates and corrective Action Requirements paragraphs IWV-3426 and 3427, respectively. Revise the relief request RRB-V17 accordingly.
2.
Excess Flow Check Valves:
SL 23-37 A-D or A-L (F, G-5)
Which is correct? The " Valve No." listing appears to have a typo. The drawing reflects A-D.
i 4
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8 3.
Check Valves and RRB-V20:
(N-7)
V 23-61 The relief request basis wording is unclear regarding assuring that the valve exercise test assures exercising the valves to the full open position.
4.
Check Valves (K-5)
V 23-12 and V 23-65 These valves need to open to drain condensate and the exhaust steam drain pot. Provide a technical justification as to why the valves aren't exercise tested?
These valves also appear to perform a containment isolation function; if so, should be Category AC and comply with IWV-3426 and IWV-3427.
5.
Check Valves (J-3)
V 23-842 and V 23-843 These valves appear to be needed to open during HPCI operation, if so, they should be exercise tested. These valves also appear to perform a containment isolation function, if so, should be Category AC and comply with IWV-3426 and IWV-3427.
6.
Relief Valves G-191169 Sh. 2 V 23-34 D-9)
V 23-66 J-12)
Provide detailed technical justification for not having these valves in the IST program, and testing the valves as required by IWV 3510.
7.
Air Operated Valve V 23-54 (K-12)
Provide detailed technical justification for not having the j
valve in the IST program and designating Category B.
8.
Check Valves (L-11)
V 23-130 and V 23-131 Provide detailed technical justification for not having these valves in the IST program and designating as Category C valves.
9.
Air Operated Valves G191169 Sh. 2 V 23-39 and 40 (M-11)
What is the safety related function of these valves?
l
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- 10. Drain Valves G191169 Sh. 1 (H-17 & J-1)
V 23-53A Air Operated H-17 V 23-42 Air Operated J-16 V 23-43 Air Operated J-16 V 23-149 CheckValve)
I-16 Provide detailed technical justification for not having these valves in the IST program.
V-15 Control Rod Drive Hydraulic System G191170 1.
Yalve V3-181 and RRB-V22 J-21 The relief request needs to incorporate testing at refueling frequency in addition to cold shutdown.
The program's valve listing drawing coordinates should be J-21, not I-21.
2.
Valves V13-115 (B-16)
The charging header check valves are active during reactor scrams to aid in control rod inserting and safe reactor shutdown. Provide detailed technical justification for not including these valves in the program.
V-16 Standby Liquid Control System Drawing No. G-191171 1.
Relief Valves SR-39A and 39B (G,K-7)
These valves should be designated Category C and tested per IWV-3510.
2.
Check Valves V 11-16 and 17 (GandH-2)
Relief Request Basis V24 refers to TS Table 4.7.2.b applicable to containment isolation valves as opposed to component operational readiness testing under Section XI IWV-3400.
Provide detailed technical justify for not testing in accordance with Section XI.
V-17 & 18 Residual Heat Removal System G-191172 1.
Motor Operated Valves: V 10-17 and RRB V26 G-8 V 10-18 F-8 a.
The relief request needs to clearly state the detailed technical basis for the specific relief requested. The relief request basis states that the valves are presently exempted, per Tech. Spec. Section 4.7.2 from leak testing, however a basis for this statement has not been found.
I 1
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b.
These valves must comply with-the Analysis of Leakage Rates and Corrective Action Requirstr.ents of the Code paragraphs IWV-3426 and IWV 3427 2.
Valves: V 10-26A/B (C-7)(C-11)
Same comment as 1.a. and b. above.
g 9
3.
Valves V10-27A/B
'(D6)(D12)
These valves are the first closed gate valves off of the reactor a
coolant loops to protect low pressure piping. Provide detailed
).
technical justification for not designating as category A and leak testing.
(Reference GDC-54) 4.
Valves V10-31A/B (C,B)-(C-10)
Same coment as 1.a. & b. above.
5.
Valve V 10-32 (C-9)
Same comment as 1.b. abase.
6.
Valve V 10-33 (A-7)
Same comment as 1.b. above.
1 7.
Valves V10-34 A/B (E-4)(E-14)
Valves V10-38 A/B (E-4)(E-13)
These valves are the first normally closed valves coming,from.
the suppression chamber (Reference GDC-54). Iame coment as 1.a. and 1.b. above.
8.
Valves V10-39 A/B (D-4)(D-14) p a.
Same comments as 1.a. and 1.b. above.
(Note:
this is the second valve from containment.)
b.
Provide detailed justification for not quarterly stroke testing these valves.
9.
Check Valves V10-46 A/B (E-7)(E-11)
These valves are listed as Category C hemvar, they are.the inside containment isoletion valves and should be categorized as AC and leak tested to assure protection of low pressure piping.
q i
a 11
- 10. Valves V10-89A/B (M-1)(L-17)
Do the valves have a fail safe position and if so, are they exercised to this position?
t 11.
Valves V10-16 A/B_
(I-6)(I-12)
These valves are the first isolation valves outside containment and as such appear to be Category A as they serve an isolation function (Reference GDC-54). Provide detailed justification for not designating Category A.
- 12. Check Valves V10-19 A-D K-6 & 12 J-6 & 12 a.
These valves are the second isolation valves outside of containment and as such it appears these valves should be Category AC and leak tested.
b.
It is not clear (Reference Note 6) that the exercise-testing verifies full opening of these valves.
13.
Relief Valves V10-SR-35 A/B (D-15)
V10-SR-40 V10-SR-72 A/B/C/D (K-11)(J-7)(J-11)
V10-SR-80 A/B K-14)
V10-SR-86 A/B K-14)
V10-RV-210 A/B D-12) D-5)
Provide detailed justification for not designating these valves Category C and testing per IWV-3510?
- 14. Motor operated Valve V10-20 (H-4)
This valve has a safety function as described in FSAR 4.8.5 "to supply either loop from the pumps in the other loop".
Its operational readiness should be verified and, therefore, included in the program.
15.
Valves i
V10-15A/B/C/D (K-7) (K-10) (J-7) (J-10)
Are these valves used to bring the reactor to a cold shutdown condition or in mitigating the consequences of an accident? If so they should be included in the program.
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-4 1
8 4'
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- 16. Valves V10-13A/B/C/D (K-8)(K-9)(J9)(J-8) y
\\ Are these valves used to bring the reactor to a cold shutdown N.
condition or in mitigating the consequences of an accident? If
~ so they should be included in the program.
\\y V 19-21 Reactor Core Isolation Cooling System (RCIC)
G191174 Sh.' 1 i
1.
Motor Operated Valves and RRB-V30 V13-15 D-7 V13-16 D-8 3
i The NRC position is that the Category A valve leak rate requirements are fulfilled by 10 CFR 50, Appendix J, require-y ments for CIVs and that relief from the Section XI leak rate
-(
testing requirements presents no safety problem. However, the licensee must comply with the Analysis of Leakage Rates i
and Corrective Action Requirements Paragraphs IWV-3426 and s
-3427 unles's specific relief is requested from these paragraphs and subsequently granted by NRC.
Revise the Relief Request.
2.
Check Valve V13-22 and RRBW31 (G-9) c
, Frequency does not include refueling frequency or (24 month
' maximum).1 Revise relief request and testing frequency.
3.
' Motor (0peratedValveV13-41 (N-10)
If this valve serves a containment isolation function with a
%g specified leak rate, it should comply with IWV 3426 and IWV-3427 (reference 1, tem 1.above).
I V
3 4.
Chec'k Valve V13-40 and RRB V-33 (N-11)
Relief request basis does not clearly state words to indicate full stroke exercise testing is required.
5.
Relief Valves G-191174, Sh. 2 i
SR-25 B-7)
SR-26 I-7)
SR-27 J-14)
Provide detailed technical justification for not including these valves in the program and testing as Category C valves as required by IWY-3510.
i 13 6.
Motor Operated Valve V-1 (13-D)
What is the safety related function of this valve?
7.
Check Valves (K13&10)
V13-70 and V13-133 Provide detailed technical justification for not including these valves in the program.
8.
Air Operated Valves V13-12 L-l'J V13-13 L-10 Provide detailed technical justification for not including these valves in the program.
9.
Air Operated Valves G 191174 Sh.1 V13-32 H-17 V13-34 K-17 V13-35 K-17 Check Valve V13-140 (I-17)
Provide detailed technical justification for not including these valves in the program.
- 10. Check Valves i
V13-SSC-10 K-8) l V13-29 J-10 V13-38 K-11 11.
RRB-V33 for valve V13-40 The alternate testing needs to be revised to clearly assure that t
the valve is full stroke exercised.
V-22 Primary Containment and Atmospheric Control 1.
Drywell to Torus Vacuum Breakers G191175 Sh. 1 (J-8)
The program list Valves V16-19-5A-J, however, the drawing indicates A-F and G&H. Which is correct?
2.
Relief Request RRB V-36
F 14 This relief request or another needs to address IWV-3420 regarding pressure differential testing at lower than functional differential pressures, IWV-3426 Analysis of Leakage Rates and IWV-3427 Corrective Action.
3.
Valves V16-19-12 A/B and RRB Y-38 G191175 Sh. 1 (K and M-16)
The relief request does not address testing at cold shutdown and refueling frequency. Quarterly exercise testing was not specified as a requirement in the valve table.
4.
Check Valves G 191175 Sh. 1 (I-11)
V16-19-51 and V 16-19-52 What is the safety related function of these valves?
V-23 Radwaste Systems G191177 Sh. I 1.
Valves V20-82, 83, 94, 95 and RRB-V39 The leak testing does not include requirements of IWV-3426 and IWV 3427 for analysis of leakage and corrective action requirements of the Code.
2.
Dry Well Sump Check Valves 80A D-2) 80B D-3 90A I-2 90B I-3 Provide detailed technical justification for not including these valves in the program and categorizing as AC.
V-24 Reactor Water Clean Up System G191178 Sh.
1.
Valves V12-15 D-2)
V12-18 D-3)
V12-68 C-11) t j
These valves are listed as Category B.
The valves serve as primary l
containment isolation valves and have a safety function to protect i
the reactor core in case of a pipe break in the clean up system.
l They isolate on a reactor water low level. These valves should be Category A and leak tested.
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15 2.
Relief Valves V12-SR-82 F-10 V12-SR-85 D-10 V12-SR-84 G-12 These valves are not included in the program, however, appear to have a safety function to protect the system against over pressurization.
What is the basis for not designating the valves as Category C and testing in accordance with IWV-3510?
3.
Check Valve V12-62 (B-5)
This valve appears to be a Category C valve since it functions to close to assure that RCIC flow goes to the core, however, it is not in the program.
V-26 Nuclear Boiler Vessel Instrumentation 1.
RRB-V40 Dwg. G-191267 The Code stipulates exercising the valves every 3 months or if the valves cannot be exercised every 3 months during plant operations, the valves shall be full stroke exercised curing cold shutdowns. The relief request for testing does not address the Code required frequency of cold shutdown nor is technical justification provided for not meeting the cold shutdown frequency.
V-27&28 Containment Atmosphere Dilution Dwg. VY-E-75-002 1.
General Comment: Valves which are required to operate or function to bring the reactor to cold shutdown conditions or in mitigating the consequences of an accident should be included in the IST program and tested in accordance with requirements of the Code (Reference IWV-1100).
If the valve is required to operate under these conditions, testing is required under the Code and any relief requested from this testing must have a technical basis provided for the specific relief requested.
(Also reference to the staff note under item 2. of Primary ContainmentandAtmosphericControl).
Further, the NRC staff has identified rapid-acting power operated valves as those which stroke in 2 seconds or less.
Relief from the trending requirements of Section XI (Paragraph IWV-3417(a) will be given for these valves since variations in stroke times will be affected by slight variations in the response time of the personnel perfonning the tests. However,
~
16 the staff does require that the licensee assign a maximum limiting stroke time of 2 seconds to these valves in order to obtain this Code relief.
The relief request bases in RRB 41, 42 and 43 lack specificity regarding the detailed technical bases for the relief requested.
These relief requests need revision.
2.
The following valves are designated as passive, however, they serve an active function with the Primary Containment Isolation System (PCIS), therefore, should be designated " Active" and exercised and stroke time tested:
VG-75A-3, 4 J-14)
VG-9 A/B G-12,I-13)
VG-22 A/B B-16,E-16)
NG-11 A/B G-9)
NG-12 A/B I-8)
NG-13 A/B I-9) 3.
The following valves are designated for alternate testing in accordance with Appendix J.
These valves need to comply with IWV-3426, Analysis of Leakage Rates and IWV-3427, Corrective Action of the Code.
FS0-109-76A/B L-14 VG-23 J-19 VG-26 J-19)
VG-9 A/B G-12,I-13)
VG-22 A/B B-16,E-16)
NG-11 A/B G-9 NG-12 A/B I-8 NG-13 A/B (I-9 4.
Technical Specifications Table 4.7.2.b require the following valves to be operable, however, the program does not operability test (exercise or stroke time) the valves. Provide detailed technical justification for not including this testing in the program.
Valves: VG-24 L-11 VG-25 L-11 VG-33 L-11 VG-34 (L-11 VG-75 A, 1-4 (J-13,J-14) 5.
Relief Valves NG-34-A, B (A-2,G-2)
l
)
17 Provide detailed technical justification for not testing these valves per requirements of IWV-3510.
V-29 TIP 1.
Ball Valves A-C and RRB V44 The program " Test Requirements" should show " leak test".
RRB-Y44 should show that the valves meet IWV-3426, analysis of Leakage Rates and IWV-3427, Corrective Action.
Quarterly testing of these valves was not stipulated as the test frequency.
2.
Shear Valves A-C The program legend stipulates testing 20% of the explosive charges every 2 years. This cumulatively test all 4 valves within eight years. Does the manufacturer's guaranteed operating life for the explosive charges exceed the eight years?
3.
Relief Request RRB-V45 The relief request will be acceptable if a maximum stroke time of 2 seconds is assigned.
(Reference comment under item 1. of V-27 & 28.)
Relief Request Basis 1.
RRB GV-2 This relief request needs better definition.
2.
RRB GV-4 As previously discussed under V-27 & 28, the NRC staff has identified rapid-acting power operated valves as those which stroke in 2 seconds or j
less. Relief from trending requirements of IWV-3417(a) will be given for these valves, however the staff does require that the licensee assign a l
maximum limiting stroke time of 2 seconds to these valves in order to obtain this Code relief.
Miscellaneous Items /Coments 1.
Provide pump and valve program listing for spent fuel pool cooling.
2.
Provide the maximum value of limiting stroke time for all power operated valves in the IST program.
s l
l l
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~
18 3.
Provide the documentation that er.sures that IWV-3300 is being met.
(Remote position indication verification).
4.
Provide latest revisions of drawings for post accideat hydrogen control and the updated IST program listing for the pumps and valves for post accident hydrogen control.
5.
Provide a listing of all valves that perform a pressure isolation boundary between the high pressure reactor coolant system and connected lower pressure piping systems.
.