ML20237K115
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Letter Sequence Approval | |
|---|---|
TAC:62753, (Approved, Closed) | |
MONTHYEARML20237K1151987-08-24024 August 1987
[Table View]Forwards List of Several Considerations Re Containment Venting Analysis That Should Be Considered When Conducting Review of Improvements Re Containment Safety Initiative Project stage: Approval ML20154K3301988-05-24024 May 1988 Forwards Rept on Containment Safety at Vermont Yankee, Describing Current Status of All Containment Improvement/ Severe Accident Initiative Items for State of Vt.Util Will Await NRC Formal Guidance Prior to Settling Accident Issues Project stage: Request ML20151Y5391988-08-24024 August 1988 Ack Receipt of Rept on Containment Safety at Facility.No Changes Identified Which Would Reduce Overall Degradation Project stage: Other 1988-05-24 |
| ML20237K115 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 08/24/1987 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Capstick R VERMONT YANKEE NUCLEAR POWER CORP. |
| References | |
| TAC-62753, NUDOCS 8708270057 | |
| Download: ML20237K115 (3) | |
Similar Documents at Vermont Yankee | |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N3901999-10-25025 October 1999
[Table view]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 Category:NRC TO UTILITY MONTHYEARML20062G6581990-11-20020 November 1990
[Table view]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 Category:OUTGOING CORRESPONDENCE MONTHYEARML20217N3901999-10-25025 October 1999
[Table view]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 |
Text
I August 24, 1987 Docket No.:
50 271
)
Mr. R. W. Capstick Licensing Engineer Vermont Yankee Nuclear Power Corporation 1617 W:wcester Road Framingham, Massachusetts 01701
Dear Mr. Capstick:
~
SUBJECT:
VERMONT YANKEE CONTAINMENT SAFETY INITIATIVE (TAC N0. 62753)
On June 25, 1987, Vermont Yankee Nuclear Power Corporation (VYNPC) submitted a status update and design description for the Vermont Yankee Containment Safety Initiative. We are studying with interest your plans to proceed with improvements related to containment spray, and look fomard to receiving more l
infonnation about your containment venting plans.
Because we consider there are several unanswered questions concerning the containment venting issue, welppreciate your thoughtful deliberate approach.
We note that you intend a thorough rereview of containment vent design and implementation issues, and that you will notify us of the results of your l
review by March 1,1988. We have enclosed a list of several considerations related to containment venting analysis that we would like you to consider in conducting your review.
1 l
Should you have any questions re Manager, V. Rooney (301-492 8344garding this please contact the NRR Project i.
Sincerely,
/s/
Steven A. Varga, Director Division of Reactor Projects I/II Office of Nuclear Reactor Regulation As stated cc:
See next page DISTRIBUTION: lDo'cket' File, local PDR, NRC PDR, SVarga, VNerses, VRooney, BBoge, TMurley,' MRushbrook, PDI-3 R/F, 0GC.Bethesda, EJordan, JPartlow, ACM ( 0), MThadani
- See previous concurrences 1)FC :PDI-3*
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- ACIDIR/PDI 3: AD/DRP*
- D/DRP
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NAME :VRooney:lm :MRushbrook :VNerses*
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.a DATE:08/8/87
- 05/ /87
- 08/ /87
- 08/ /87
. 8 0 /87 0FFICIAL RECORD COPY 8708270057 G70824 PDR ADOCK 05000271 p
PDR U
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'i 1
Docket No.: 50-271
)
Mr ' R..W. Capstick i
'Lic sing Engineer Vermo t Yankee Nuclear Power Corporation 1617 W cester Road Framingh
, Massachusetts 01701
Dear Mr. Ca tick:
SUBJECT:
VERM iT YANKEE CONTAINMENT SAFETY INITIATIVE (TAC NO. 62753)
On June 25, 1987, ermont Yankee Nuclear Power Corporation (VYNPCI submitted a status update and sign description for the Vemont Yankee-Containment Safety Initiative. We are tudying with interest your plans to proceed with improvements related containment spray, and look forward to receiving more information about your ntainment venting plans.
Because we consider the co tainment venting issue to be fraught with conflicting safety objectiv
+nd-to be more complex than the containment spray issue, we appreciate yo r thoughtful deliberate approach, We' note that you intend a thorough rereview f containment vent design and implementation issues, and that you will notify us of the results of your review by March 1, 1988. We have enclosed a list of everal considerations related to containment venting analysis which may be of us to you in conducting your review.
.Should you have any questions regardi this please contact the NRR Project Manager, V. Rooney (301-492-8344).
Sin rely, j
Steven A.
rga, Director Division of eactor Projects I/IT Office of Nuc ar Reactor Regulation cc: See next page DISTRIBUTION: _ Docket File, Local PDR, NRC PDR, SVarga, VNerses, Vkooney, BBoger, MRushbrook, PDI-3 R/F, GC.Bethesda. EJordan, JPartlow, ACRS (10) rq A/
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OFC :PDI.3( /
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- ACTDIR/PDI.3:A
- D/DRP NAME :VRoo/t %.:......
ney:Im :MRus ok :VNerses oger
- SVa rga DATE :08//)S/87
- 08 187
- 08/A0/87
- 08,/LP /87
- 08/ /87 OFF.ICIAL RECORD COPY
't Enclosure CONTAINMENT VENTING CONSIDERATIONS A thorough review of considerations involved in containment venting would
. include:
1)
A comprehensive analysis of accident sequences, with their estimated frequency.of occurrence, for which the vent would be called upon to operate.
2)
An estimate of the fraction of those sequences where the vent would be operated but where the accident would have been terminated short of containment failure without vent operation:
(a) electric power returned to service (b) equipment returned to service (c) mis-diagnosed situation corrected by operators 3)
A comprehensive analysis of sequences that (a) could be improved by correct use of the vent, or (b) could be initiated or made worse by incorrect operation of the vent 4)
An analysis of sequences that could lead to containment failure by operation of the vent followed by excessive pressure differential (buckling).
5)
Analysis of the probability of vent failure when called upon.
6)
Analysis of maintenance or surveillance errors on the vent system that could induce accidents.
7)
An estimate of the radioactivity released for all sequences when the vent could be opened, including both correct usage according to procedures and incorrect usage due to human error or equipment malfunction.
l l
l
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