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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-99-110, Informs of Util Intent to Replace Commitments Made in Licensee & Subsequently Ack in NRC with Containment Insp Criteria Defined in 10CFR50.55a(b)(2)(vi),per Drywell Coating Insp1999-08-31031 August 1999 Informs of Util Intent to Replace Commitments Made in Licensee & Subsequently Ack in NRC with Containment Insp Criteria Defined in 10CFR50.55a(b)(2)(vi),per Drywell Coating Insp BVY-99-111, Informs That Encl TS Bases Page 91 Has Been Revised to Allow Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line Uncorrected Solution & on-line 3D-Monicore Exposure Corrected Solution1999-08-31031 August 1999 Informs That Encl TS Bases Page 91 Has Been Revised to Allow Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line Uncorrected Solution & on-line 3D-Monicore Exposure Corrected Solution ML20211G4791999-08-27027 August 1999 Forwards Notice of Withdrawal of 990420 Amend Request Re TS on Reloading & Unloading Sequence of Fuel in Reactor Core When All Fuel Removed from Core BVY-99-107, Submits Response to NRC RAI Re Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355 Fuel Assemblies1999-08-26026 August 1999 Submits Response to NRC RAI Re Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355 Fuel Assemblies ML20211E8841999-08-25025 August 1999 Requests That Licensee Provide bldg-specific Justification for Use of Method A.1 at Locations Where Amplification Significantly Exceeds 1.5 Limit Above 8 Hz ML20211E1371999-08-20020 August 1999 Forwards from J Bean to H Miller & FEMA Final Exercise Rept for 990427-29 Plume Exposure & Ingestion Pathway Exercise for Vermont Yankee Nuclear Power Station.No Deficiencies Noted.Areas Requiring C/A Identified ML20211H0851999-08-19019 August 1999 Forwards Insp Rept 50-271/99-12 on 990628-0711 & Nov. Violation Re Failure to Monitor Unavailability of Specific Sys,Structures & Components During Refueling Outage Did Not Allow Adequate Assessment of Maint Effectiveness BVY-99-108, Requests That Gv Bogue,Bj Croke,Vs Ferrizzi,Me French, Bk Mcnutt,Jf Meyer & DM Navarro Take BWR Gfes of OL Exam Administered on 991006.DA Daigler & ST Brown Will Have Access to Exams Before Tests Administered1999-08-19019 August 1999 Requests That Gv Bogue,Bj Croke,Vs Ferrizzi,Me French, Bk Mcnutt,Jf Meyer & DM Navarro Take BWR Gfes of OL Exam Administered on 991006.DA Daigler & ST Brown Will Have Access to Exams Before Tests Administered BVY-99-103, Informs That Util Expects to Submit Approx Twenty Licensing Actions in FY00 & FY01,in Response to Administrative Ltr 99-021999-08-18018 August 1999 Informs That Util Expects to Submit Approx Twenty Licensing Actions in FY00 & FY01,in Response to Administrative Ltr 99-02 BVY-99-100, Forwards Revised Floor Response Spectra Diagrams,Originally Sent as Attachment 1 to Licensee to Nrc.Revised Diagrams Have More Legible Scale Markings1999-08-0202 August 1999 Forwards Revised Floor Response Spectra Diagrams,Originally Sent as Attachment 1 to Licensee to Nrc.Revised Diagrams Have More Legible Scale Markings ML20210M5791999-07-30030 July 1999 Responds to NRC 990726 Telcon Re Status of Resolution for USI A-46 Outliers.Written Summary,By Equipment Category, Listed ML20211E1701999-07-28028 July 1999 Forwards Copy of Final Exercise Rept for 990427-29,full- Participation Plume Exposure & Ingestion Pathway Exercise of Offsite Radiological Emergency Response Plans site-specific to VYNPS ML20210G5041999-07-27027 July 1999 Responds to NRC 990301 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions. Licensee Will Submit Info Re Proposed Sys Mod by 990916 ML20210J3031999-07-27027 July 1999 Submits Proposed Changes to Eals.Attachment 1 Provides Listing of Changes to EALs Along with Ref to Bases Documents Supporting Change ML20210G4271999-07-27027 July 1999 Forwards Testing Data & Associated Results for Fitness for Duty Program at Plant for 990101-0630 ML20216D7321999-07-26026 July 1999 Forwards Insp Rept 50-271/99-05 on 990510-0620.Two Viiolations Being Treated as Noncited Violations ML20209G2721999-07-14014 July 1999 Discusses Licensee Response to RAI Re GL 92-01,Rev 1,Suppl Suppl 1, Rv Structural Integrity, for Vermont Yankee Nuclear Power Station ML20209J0601999-07-14014 July 1999 Forwards Rev 11 to Vols 1-10 of State of Nh Radiological Emergency Response Plan & Vols 11-50 to Town Radiological Emergency Response Plans,In Support of Vermont Yankee & Seabrook Station.Vols 17-19 of Were Not Included ML20209G6931999-07-14014 July 1999 Forwards Request for Addl Info Re Spent Fuel Storage Capacity Expansion ML20209G1531999-07-12012 July 1999 Discusses Util Setpoint Control Program Implementation Schedule,As Committed to in Licensee 990514 Response to Notice of Violation,Insp Rept 50-271/97-10 ML20196J2321999-06-30030 June 1999 Submits Input from Util Technical Staff Re Soil Disposal on-site Under 10CFR20.2002 & Expresses Interest in Pursuing Approval to Use Same Methodology (Implemented Through Util ODCM & Reported as Noted) If Possible ML20196J7421999-06-29029 June 1999 Informs NRC That Vygs Has Implemented Severe Accident Management,As Committed to in Licensee to NRC ML20209B6111999-06-29029 June 1999 Resubmits Summary of Vynp Commitments Page to Replace Original Page Submitted with Responding to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20196J2431999-06-29029 June 1999 Informs That Author Received Call from NRR on Dirt Spreading Ltr & Questions Re Cover Ltr Statement Where Util Asks to Be Allowed to Dispose of Future Soil in Same Manner Provided Same Acceptance Criteria Met ML20209C3751999-06-28028 June 1999 Forwards non-proprietary Rev 16 to EPIP OP 3524, Emergency Actions to Ensure Initial Accountability & Security Response & Proprietary Rev 12 to EPIP OP 3531, Emergency Call-In Method. Proprietary Encl Withheld ML20209B5861999-06-28028 June 1999 Provides Alternative Y2K Readiness Status Described in Supplement 1 to GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure Rept Encl ML20196G5241999-06-22022 June 1999 Responds to Re Changes to Vermont Yankee Guard Training & Qualification Plan,Rev 8,Errata A.No NRC Approval Is Required.Encl Will Be Withheld from Public Disclosure Per 10CFR73.21 BVY-99-084, Forwards Proprietary Application & Medical Certificate for Mod of Listed SRO License,For Gj Leclair.Gj Leclair Will Be Trained & Evaluated in Accordance with Util Lsro Training Description.Proprietary Info Withheld,Per 10CFR2.7901999-06-18018 June 1999 Forwards Proprietary Application & Medical Certificate for Mod of Listed SRO License,For Gj Leclair.Gj Leclair Will Be Trained & Evaluated in Accordance with Util Lsro Training Description.Proprietary Info Withheld,Per 10CFR2.790 ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20195H1741999-06-15015 June 1999 Forwards Original & Copy of Request for Approval of Certain Indirect & Direct Transfer of License & Ownership Interests of Montaup Electric Co (Montaup) with Respect to Nuclear Facilities Described as Listed 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217F1261999-10-12012 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 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 ML20216J3531999-09-29029 September 1999 Responds to NRC Re Violations Noted in Insp Rept 50-271/99-12 on 990628-0811.Corrective Actions:Based on RFO 20 Maint Rule Outage Performance Review,Task Was Generated to Clarify & Enhance SD Monitoring Process BVY-99-122, Notifies of Intention to Reinstate Original Version of App F in FSAR & Correct Docket Re Assumption That Electrical Power Sys Are Designed IAW Requirements of GDC-171999-09-28028 September 1999 Notifies of Intention to Reinstate Original Version of App F in FSAR & Correct Docket Re Assumption That Electrical Power Sys Are Designed IAW Requirements of GDC-17 BVY-99-113, Requests Approval to Perform Alternative Testing to That Specified by ASME Boiler & Pressure Vessel Code,Section XI & Asme/Ansi OM, Operation & Maint of Nuclear Power Plants. Attachment 1 Provides Justification for Alternative Testing1999-09-21021 September 1999 Requests Approval to Perform Alternative Testing to That Specified by ASME Boiler & Pressure Vessel Code,Section XI & Asme/Ansi OM, Operation & Maint of Nuclear Power Plants. Attachment 1 Provides Justification for Alternative Testing BVY-99-114, 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-99-116, 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 BVY-99-115, Forwards non-proprietary & Proprietary Responses to 990714 RAI Re Civil & Mechanical Engineering Considerations for Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355.Proprietary Encls Withheld1999-09-16016 September 1999 Forwards non-proprietary & Proprietary Responses to 990714 RAI Re Civil & Mechanical Engineering Considerations for Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355.Proprietary Encls Withheld BVY-99-118, Responds to RAI Concerning GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions1999-09-16016 September 1999 Responds to RAI Concerning GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions 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 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 BVY-99-108, Requests That Gv Bogue,Bj Croke,Vs Ferrizzi,Me French, Bk Mcnutt,Jf Meyer & DM Navarro Take BWR Gfes of OL Exam Administered on 991006.DA Daigler & ST Brown Will Have Access to Exams Before Tests Administered1999-08-19019 August 1999 Requests That Gv Bogue,Bj Croke,Vs Ferrizzi,Me French, Bk Mcnutt,Jf Meyer & DM Navarro Take BWR Gfes of OL Exam Administered on 991006.DA Daigler & ST Brown Will Have Access to Exams Before Tests Administered BVY-99-103, Informs That Util Expects to Submit Approx Twenty Licensing Actions in FY00 & FY01,in Response to Administrative Ltr 99-021999-08-18018 August 1999 Informs That Util Expects to Submit Approx Twenty Licensing Actions in FY00 & FY01,in Response to Administrative Ltr 99-02 BVY-99-100, Forwards Revised Floor Response Spectra Diagrams,Originally Sent as Attachment 1 to Licensee to Nrc.Revised Diagrams Have More Legible Scale Markings1999-08-0202 August 1999 Forwards Revised Floor Response Spectra Diagrams,Originally Sent as Attachment 1 to Licensee to Nrc.Revised Diagrams Have More Legible Scale Markings ML20210M5791999-07-30030 July 1999 Responds to NRC 990726 Telcon Re Status of Resolution for USI A-46 Outliers.Written Summary,By Equipment Category, Listed ML20211E1701999-07-28028 July 1999 Forwards Copy of Final Exercise Rept for 990427-29,full- Participation Plume Exposure & Ingestion Pathway Exercise of Offsite Radiological Emergency Response Plans site-specific to VYNPS ML20210G5041999-07-27027 July 1999 Responds to NRC 990301 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions. Licensee Will Submit Info Re Proposed Sys Mod by 990916 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 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 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 ML20196J7421999-06-29029 June 1999 Informs NRC That Vygs Has Implemented Severe Accident Management,As Committed to in Licensee to NRC ML20209C3751999-06-28028 June 1999 Forwards non-proprietary Rev 16 to EPIP OP 3524, Emergency Actions to Ensure Initial Accountability & Security Response & Proprietary Rev 12 to EPIP OP 3531, Emergency Call-In Method. Proprietary Encl Withheld ML20209B5861999-06-28028 June 1999 Provides Alternative Y2K Readiness Status Described in Supplement 1 to GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure Rept Encl 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 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 ML20195C5891999-05-27027 May 1999 Forwards Response to NRC 990301 RAI Re GL 96-05 Program at Vermont Yankee Nuclear Power Station ML20195D5341999-05-27027 May 1999 Forwards Description of Vermont Yankees Plans for Insp of & Mods to Certain Reactor Vessel Internals BVY-99-074, Forwards Application & Medical Certificate Required for Renewal of Jd Livingston,License OP-10049,RO License.Medical Certificate Withheld1999-05-26026 May 1999 Forwards Application & Medical Certificate Required for Renewal of Jd Livingston,License OP-10049,RO License.Medical Certificate Withheld ML20195B4081999-05-24024 May 1999 Withdraws Licensee Commitment,Contained in ,To Reinitiate ITS Project Following Completion of FSAR Accuracy Verification Project.Util Will Continue to Modify Current TS with Number of Improvements BVY-99-067, Informs That Bw Metcalf,License SOP-1761-9,has Retired from VYNPS & Will No Longer Require License.Nrc Is Requested to Terminate License1999-05-21021 May 1999 Informs That Bw Metcalf,License SOP-1761-9,has Retired from VYNPS & Will No Longer Require License.Nrc Is Requested to Terminate License ML20196L1801999-05-18018 May 1999 Withdraws Licensee & Attachment,Containing Rev 2 to Vermont Yankee Operational QA Manual, from Further Consideration by Nrc.Summary of Commitments Encl ML20206K3201999-05-0707 May 1999 Forwards Response to RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML20206J2801999-04-30030 April 1999 Forwards 1998 Annual Financial Repts for CT Light & Power Co,Western Ma Electric Co,Public Svc Co of Nh,North Atlantic Energy Corp,Northeast Nuclear Energy Co & North Atlantic Energy Svc Corp,License Holders ML20206D3731999-04-27027 April 1999 Informs NRC of Changes in Recipients of NRC Docketed Correspondence ML20206B1401999-04-23023 April 1999 Forwards Replacement of Section 3(a) of NSHC Determination Provided by Re TS Proposed Change 208,suppl Section 6 ML20205S3381999-04-16016 April 1999 Submits Revised Schedule for Response to NRC 990226 RAI Re 980630 Submittal of IPEEE Rept.Info Will Be Submitted by 991231 ML20205S3891999-04-16016 April 1999 Forwards non-proprietary & Proprietary Revised Page to Holtec Rept HI-981932,supplementing TS Proposed Changed 207 Re Spent Fuel Pool Storage Capacity Expansion ML20205S3031999-04-15015 April 1999 Forwards Revised TS Bases Pages 90,227,164 & 221a,accounting for Change in Reload Analysis from Yaec to GE Methodology, Reflecting Change in Condensation Stability Design Criteria & Accounting for More Conservative Calculation ML20205P9291999-04-14014 April 1999 Requests That Rev to NRC 821029 SER for NUREG-0737,Item II.K.3.24,be Issued to Clarify Util Installed RCIC & HPCI HVAC Configuration,As Discovered During Preparation of DBDs for Sys ML20205P8191999-04-13013 April 1999 Forwards Rev 2 to COLR for Vermont Yankee Cycle 20, Dtd Feb 1999,IAW TS Section 6.7.A.4 ML20205M3191999-04-0707 April 1999 Forwards 1998 Annual Rept of Results of Individual Monitoring, Per 10CFR20.2206(b).Licensee Is Submitting Matl to Only Addressee Specified in 10CFR20.2206(c).Without Encl ML20205K0351999-03-31031 March 1999 Informs That Certain Addl Corrections Warranted for 990121 SER for Amend 163 to License DPR-28 Re Suppression Pool Water Temp.Suggested Corrections Listed ML20205K1821999-03-31031 March 1999 Informs of Modifications That Util Made to CO(2) Fire Suppression Sys,Due to Sen 188 Which Occurred at Ineel on 980728.Compensatory Actions Will Remain in Place Until Modifications Are Complete & Systems Are Returned to Svc ML20206A6951999-03-29029 March 1999 Request Confirmation That No NRC Action or Approval,Required Relative to Proposed Change in Upstream Economic Ownership of New England Power Co,Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee 1999-09-29
[Table view] Category:RESEARCH INSTITUTION/LABORATORY TO NRC
MONTHYEARML17347B6821987-02-0505 February 1987 Forwards Draft Beyond DBA in Spent Fuel Pools (Generic Issue 82). Formal Nureg/Cr Will Be Completed After NRC Review ML20080A8431983-07-21021 July 1983 Forwards Info Re Remaining Unresolved Technical Issue to Be Raised in Upcoming Field Insp Concerning Possibility of Fire Causing Secondary Leads of Current Transfer to Open W/ Possible Adverse Effects on Alternative Safe Shutdown ML20042A0241981-12-29029 December 1981 Forwards Initial Review of Util steady-state Fuel Performance Code (Frosstey).Recommends Frosstey Be Subj to Further Evaluation ML20042A0191981-10-0707 October 1981 Comments in Response to 810818 Ltr Re RIS0 Tests 022 & 013 ML19305E3791980-04-14014 April 1980 Forwards Results of Fire Protection Review,Item 3.1.8,fire Barrier Penetations.Recommends NRC Consider Design & Const of Penetration Seals as Conditionally Acceptable.Typical H Penetration Requires Addl Test Data ML19305D3311980-04-0808 April 1980 Forwards Assessment of Fire Protection Review Re Item 3.1.13,portable Ventilation Equipment.Licensee Input Has Not Been Received.Recommends That Ventilation Equipment Be Installed ML19312D1911980-03-17017 March 1980 Forwards BNL Input to Plant Fire Protection Review,Items 3.1.4,3.1.6,3.2.5,3.2.2,3.3.3 & 3.1.14.Water Suppression Sys,Gas Suppression Sys,Flame Retardant Coatings & Air Breathing Apparatus Are Satisfactory & Should Be Accepted ML19309B6631980-01-31031 January 1980 Forwards Notes of 800129 Meeting W/Util 1987-02-05
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'RE: { Vermont: Yankee, Fire Protection! Review, Items 3.1.4, 3.1.6, 3.2.5, 3.2.2,.
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Enclosed is the' Brookhaven National Laboratory input to Vermont Yankee for all the items that- we have on hand that were-not previously completed.
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. n D[[ IThe=SER; states thatl a manual' dryl pipe water'. sprinkler system will-~ be provided-E d "'
6 f rP each : diesel igenerator; room. An area preaction water sprinkler system wil_1
[be5provided'at-theTcable penetration?areaLat grade: elevation in the reactor ~
Jv 'buildi.ng.= The turbine building : lay-down area used for parking motor vehicles -
;willE be: protected byJan automatic sprinkler-system or motor vehicles will. not ibelstoredginL this area. The diesel 1 driven fire pumo will be. isolated from the
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- electric moto'r driven fire. pumpJand; service: water pumps by the-addition of a -
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- noncombustiblefwalixequivalent- to afone-hour fire ' rating with the top ~ opening
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[ protected by aniautoi.ctic water sprinkler system.
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10esignjetails;on .3.1~ 4 Water Suppression Systems.were submitted by the - .
clicensee on August -14,c 1978~ and January;17,1980. - The~ information. included t L(1) dry / pipe sprinkler system foriea'c h diesel generator-room (2) sprinkler:
. ' Jsystem. for: cable p' enetration area'(3) deluge system for. turbine building lay-idownfarea, and;(4) sprinkler system over diesel fire pump area.
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i ThE 6asic design _ criteria for. the manual _ dry pipe water' system were-accepted-
<by us in!our: letter to you of January 10,.1980.- The balance of the design for
. the di6sel ' generator rooms ,is . satisfactory. and.we _ recommend that the staff .ac-
? cept this' item.,z We;are'notVaddressing the fire: barrier here; no'.information has been; submitted,to date.
< . tThe~ design:for=preaction.systemLprotection'theLcable penetration is satisfac-y tory /provi.di_ng. the following- recommendations. are impiemented:
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'W ,l , s a. :The'waterJfeed to the. preaction system is independent of the hose sta-o . . ition'supplyLin the area of; protection so that the p' reaction system -
m c pressure willinot.;be seriously- reduced when the nearby hose stations are'used.-
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;bE DActuation of..the system is by smoke ~ detectors since thisl type of de-
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Jtector:is most: responsive to. cable fires.
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iThel design for7the automaticideluge system protecting the turbine laydown area 1
iis? acceptable contingent Lupon early: wa'rning . detection:for system actuation.
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LTh' ear'lyWarnifng? detection ;shoul d be i appropri ate for, the combustibl es i nvol ve*
- s Jand ~we- recommend;that the' details f of; this detection" system be' submitted to the -
- - ?staffrforfreview.1 ^ ~
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- The design:for the?s~prinkisrosystem protectingLthe di.esel fire pump .is accept .
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,,-- fabl e iprovidi ng;thelfoll owi ng} recommendations t are impl emented. " _
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Cprovided;for :this.: system 'so' that the operators Lwill3know that- the -sys '
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l Jf' Lb.MThe feed forithe system.sh'oul'd[be: on- the system side of the. pump.- d itolation valves so that the sprinkler will not be disabled during l (diesel' fire pump maintenance.~ ~ l
~B.ased Opon:the' above review we- find 3.1.4_ Water Suppression Systems. satisfac-tory;and:we recommend that the staff: accept this item.
Item 3.1.6 D' - Gas Suppression Systems
;The'SER states that the CO2 system for the cable spreading area and enclosed
-battery room 'will- be modified to make it an automatically actuated system. . An K : automatic CO2 suppression system will be provided in the switchgear room.
<This system will be used ~to provide a backup manually actuated system for.the cable spreading area. The diesel; driven fire water pump day tank room will be
- protected by;an automatic l gas: suppression system.
- 0n January 10, 1980 an acceptance letter was forwarded by BNL to the staff on
<3'.1.6,; Gas Suppression' Systems. In this ' letter. approval was given for chang-ing the gas suppression system in the diesel fire pump _ day tank room to auto-matic sprinklers.- The licensee's January 17, 1980 submittal indicates the
. diesel fire pump. day tank room will: be protected by an automatic carbon diox-ide system actuated by the-existing. flame detector within theiroom. A 507, concentration ~will-be obtained within the room.-
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. Based upon the above review we find the gas suppression _ system protecting the 1 diesel fire' pump day. tank room acceptable to;us and'we recommend that.the
- staff accept this partiof item 3.1.6..
The above1 referenced January 10~, 1980 letter also approved the design criteria
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for the gas suppression systems in the' cable spreading room (including battery.
froom)'and switchgear room. The only exception was covered under 3.2.5, Gas '
- Suppression System of.the SER.- Thisiwas on-sequence.of detector. response for system actuation. ' The licensee ~ under cover-letter ' dated January 17, 1980 ad-
' dressed the' actuation sequence.~ This has now been satisfactorily answered under item 3.2.5.
'These parts of. item 3.1'.6 is now~ satisfactory and we recommend that the staff
. accept:it.-
Item-3.2.5:- Gas Suppression Systems _
-Section 3.2.5'of- the. SER requires' the licensee to provide design criteria for the automatic actuation of carbon dioxide systems -in the cabl.e spreading room 3 cluding battery room)- and switchgear room. ' Included in this criteria will
- helinterlock features incorporated to insure personnel _ life . safety when king;in~the_ area.-
cThe'11censee'sisubmittal, dated Septemb'er 14, 1979, indicated that system
; actuation 'for:both . areas protected. by carbon dioxide will ' be .similar. A' pro-
- posed ionization detection. system using Lthe counting principal would actuate Jthe~ s~uppression system in each area.; The: counting module was set _ to receive f threeisuccessive alamsibefore: system actuation. Onithe receipt of each sig-
- inalJfrom a~ detector the: fire ~alam control ' panel initiated ~a response func-
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. . iThe firstLdetector'act'uated causes local: alarm bells and local and remote
-fannunciation ofca fire sign' l.a _ Remote annunciation will -be in the control
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.roombThe second detector actuated causes automatic closure ~of associated fire
; dampers; and room exhaust fans. The thirc Jetector actuated causes carbon idioxideldischarge-into the ' protected area and'provides local and remote indi-
; cation that the carbonidioxideLsystem has been activated.
Both the.' detection- system and the. trip circuit (including at ort -switch) will
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"be. electrically; supervised.tolannunciate a trouble: signal in the control room.
- The' backup suppression system for the. cable ~ spreading area is the switchgear
. room CO 2 . system. eThis.will be. actuated 'by a manual pull: station.
Bothisystems'willlhaveLa thirty (30) second time delay before actual discharge
.of_the suppressing agent. This will all'ow sufficient evacuation time for per-
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sonnel within the-area. :0n' each system an override switch will be provided to L enable-local ~~ control for manual firefighting. - Use 'of these-switches will be strictly controlled by firefighting: training ~ and procedures.
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.We have. reviewed the design. drawings "or detector location, , pacing and actua-tion; sequence. Twondetectors will be located in.each deep beamed area in the
'switchgear. room while. detectors are located over high cable concentrations in Lthe cable ~ spreading.roomf and ov'er the penetration area of the cable spreading
. room. The detection system is presently programmed for three detectors to
. actuate before carbon dioxide is released. With this _ logic, and the uncer-
- tainties in detector siting due to the room geometry, the response time in certain areas may ~be too long because.of ceiling obstructions. ' The delayed discharge may allow the fire to obtain a foothold and become deep seated.
- Theidetectio'n system has the flexibility to initiate discharge of the suppres-
. sing agent on the first, second or. third detector. actuation. The licensee in their January;17,1980. letter has -committed to change the sequence of opera-
.. tion.= 'The first detector.will- initiate the closing of' dampers, shutdown of
' fans and annunciate Lin the control room.- The second detector to slann will initiate the operation of the gas suppression system.
'We find the design ofithe detection system for. initiation of the various gas:
. suppression systems satisfactory andl recommend that the staff accept this- i item.= j Item 3.2.2 - Flame ' Retardant Coatings < .
The.use of flame retarda'nt coatings' on electrical cables in trays and risers-
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in the:switchgear ruom has been. recommended by the staff. ' The licensee will i evaluate:the . impact of flame retardant coatings on cable.derating to determine i
, . if: sufficient design l margin ex1sts to use this' method to improve the fire _ re-
= sistanceJof electrical: cables..
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! The71icensee submittal l dated?Januaryz 30,11978, indicate! that' the~ application t Lof ~aifire retardant. coating to all ? electrical .: ables in the switchgear room is
'not feasiblen LThe cables.'do'not have. sufficient decating _ margin for safe E _ loperationfof:thewnit.~
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- 3Theilicansee has' committed to providing _an automatic total flooding. carbon dioxide : suppress'on system within-the. room. ' The system will be actuated by smoke! detectors and discharge sufficient carbon dioxide to maintain a 50% con-
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? centration fori10 minutes.
LThellicensee's September:14,1979 letter indicated they would coat the cable
- in cable trayLat'divis'ional crossovers. The' cables will be coated for a mini-mum 4 distance of 5Jfect beyond the nearest. redundant' division cables. A fire
. stop'.will .be provided in any conduit' connecting one safety train to another.
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> In(addition, where conduit containing safety related cable from one division crosses cable tray containing safety related. cables from a redundant: division in:the;Switchgear Room, Vermont Yankee will provide a_ shield.. This shield twill consist- of a fire retardant coating' on the cables.in the tray. The coat-Li ng williextend to,a minimum ~of 2-1/2: feet beyond the conduit crossing.
fBaseduponthe'abovereview,wefindthe~ licensee'scommittmentincoating.
7 selective cables in certain areas and configurations acceptable and recommend that-the-staff ~ accept this 1_ tem.
Item 3.2.3 - Fire Water 1.oop-The SER1 states that the licensee is evaluating the alternatives to. maintain an adequate. supply of-fire water in the ~ event of a failure in'one of the fire water feeds which'is located next to and may damage the redundant feed to the underground loop.
"The' licensee -responded to the SER provision on September 14,-1979 and again_on January .17,1980 by stating that no modifications are required based on var-
-ious . installation features. The licensee: stated that calculations were made to back up their^ cosition; however no calculations were supplied.
We suggest that due to their very close proximity, the two mains could bc lost Ictithe same: time thereby endangering .all fire protection water supply. In
-order to' support at our position, we recently contacted the. Suffolk County-N Water Authority, the American Iron and Steel Institute, the Cast Iron and Pipe
-Research Association and the American Water Works' Association. . The consensus-of;opin. ion that we-got from-these contacts was th'at good water main separation
'was essential 1 so that one bad leak and wash-out wouldn't disable the other
' main; good separation was' considered to be 20-20 feet and'not the few feet of separati.on normally found in a trench.-
We_.~ recommend th'at the staff require a minimum fire main' separation of_ 25 feet at. spectfied ~in:the. ANS/ ANSI; standard 59.4.
- Item'3.1.14 '-rAir Breathing Apparatus The SER state' s tha't the capabilityito maintain a supply of; breathing- air for a
. fire;emergencyfuse will' be upgraded to coverta' minimum time Linterval of six
^ hours. !Self-contained breathing' apparatus, including spare bottles,'will be' r _ Eplaced Lfor ready access ~ byfcontroleroom personnel . .
Theilicensee responded in their January 17,1980 letter that Vermont- Yankee -
lhasipurchasedffive BioPak.60P's for fire'_ brigade _use. The BioPak 60P -sup- ,
? plied by BioMarine Industries', Inc., is'.a closed circui_t oxygen breathing '
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gapparatusi; tItfis a:: positive pressure. device, 'andLwill supply more than sixty.
~ * ' sminutes'of breathing time from ~each;oxygentbottle. Sufficient-spare oxygen
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lbottles'-and Carbon' Dioxide Absorbers have been purchased' to supply.six . hours.
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y . ': of(breathing: time.forJeach;of the five shift fire brigade members.
This answer"is . satisfactory?as to the amount of breathing air ~available. How-ever, the-licensee did ~not: address'the requirement 1 for placing the,.self con-
'tained breathing / apparatus..for ready access by control room personnel. 'We isuggest,that the. staff' request:the licensee to. document that this part of tihe item has'been~done. -We recommend-that;the-. staff' accept.this item based.on the fulfillment :of thisfrequirement. ,
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