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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:UTILITY TO NRC
MONTHYEARML20059J2831990-09-10010 September 1990 Forwards Updated Operator Licensing Exam Schedule for FY91, FY92,FY93 & FY94,per Generic Ltrs 90-07 & 89-12 ML20059D9831990-08-28028 August 1990 Forwards fitness-for-duty Program Performance Data for 900103-0630,per 10CFR26.71.NRC Review of Data Will Provide Realization That Positive Testing Rate Extremely Low & Limited to pre-access Testing Population BVY-90-087, Forwards Addl Info on Use of RELAP5YA Program for LOCA Analyses.Proprietary Encl Withheld1990-08-28028 August 1990 Forwards Addl Info on Use of RELAP5YA Program for LOCA Analyses.Proprietary Encl Withheld BVY-90-086, Responds to NRC Re Violations Noted in Insp Rept 50-271/90-06.Corrective Actions:Incident Rept Initiated & All Required Locking Devices in Place by 9007061990-08-24024 August 1990 Responds to NRC Re Violations Noted in Insp Rept 50-271/90-06.Corrective Actions:Incident Rept Initiated & All Required Locking Devices in Place by 900706 ML20059F6681990-08-22022 August 1990 Comments on Review of Amend 115 to License DPR-28,including Safety Evaluation.Requests Explanation of Statement in NRC Re How NRC Considers Comments & What Resolution Could Be for Each Util Comment in BVY-90-085, Informs That Sys Testing & Operator Training Successfully Completed & SPDS Declared Operable on 900813.Util Intends to Operate SPDS in Parallel W/Original Honeywell Gepac Plant Computer Until mid-Nov 19901990-08-15015 August 1990 Informs That Sys Testing & Operator Training Successfully Completed & SPDS Declared Operable on 900813.Util Intends to Operate SPDS in Parallel W/Original Honeywell Gepac Plant Computer Until mid-Nov 1990 BVY-90-084, Notifies NRC of Intentions to Install Test Fuel Assemblies & Test Control Blades During Cycle 15 Refueling Outage in Sept 19901990-07-24024 July 1990 Notifies NRC of Intentions to Install Test Fuel Assemblies & Test Control Blades During Cycle 15 Refueling Outage in Sept 1990 BVY-90-082, Informs That Effective 900723 Facility Implemented Rev 4 of Procedure Generating Package & Corresponding Revs to Eops. Revs Developed Per Rev 4 of BWR Owners Group Emergency Procedure Guidelines1990-07-24024 July 1990 Informs That Effective 900723 Facility Implemented Rev 4 of Procedure Generating Package & Corresponding Revs to Eops. Revs Developed Per Rev 4 of BWR Owners Group Emergency Procedure Guidelines BVY-90-071, Forwards Rev 2 to Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21)1990-07-20020 July 1990 Forwards Rev 2 to Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21) BVY-90-078, Forwards List of Refs for Proposed Change 161 to Facility OL & Tech Specs1990-07-17017 July 1990 Forwards List of Refs for Proposed Change 161 to Facility OL & Tech Specs BVY-90-072, Forwards Supplemental Effluent & Waste Disposal Semiannual Rept for Third & Fourth Quarters 1989,Including Annual Radiological Impact on Man for 19891990-06-27027 June 1990 Forwards Supplemental Effluent & Waste Disposal Semiannual Rept for Third & Fourth Quarters 1989,Including Annual Radiological Impact on Man for 1989 ML20043G4351990-06-15015 June 1990 Requests Temporary Waiver of Compliance from Tech Spec Requirements for Limiting Conditions for Operation for Certain post-accident Monitoring Instrumentation Listed in Tech Spec Table 3.2.6.Parameters Listed ML20043E4011990-06-0808 June 1990 Responds to Second Request for Addl Info on Use of RELAP5YA. Explanation Re Why More Accurate View Factor Calculation Not Included in Huxy Code Addressed ML20043C6131990-06-0101 June 1990 Forwards YAEC-1659-A, Simulate-3 Validation & Verification. ML20043C5991990-06-0101 June 1990 Forwards Accepted Version of YAEC-1683-A, MICBURN-3/ CASMO-3/TABLES-3/SIMULATE-3 Benchmarking of Vermont Yankee Cycles 9 Through 13. ML20043C4821990-05-30030 May 1990 Informs of Three Organizational Changes That Will Become Effective on 900601.WP Murphy,Jp Pelletier & DA Reid Will Be Senior Vice President of Operations,Newly Created Vice President of Engineering & Plant Manager,Respectively ML20043B7561990-05-23023 May 1990 Informs That Util Intends to Utilize Relationship Between Frosstey & FROSSTEY-2 to Support Cycle 15 Calculations.Nrc Approval of FROSSTEY-2 Needed by Aug 1990 for LOCA Analysis Program ML20043B6481990-05-17017 May 1990 Forwards Rev 19 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) BVY-90-058, Forwards Public Version of Vermont Yankee Nuclear Power Station Emergency Response Preparedness Exercise 1990. Exercise Scenario Package Includes All Info Pertinent to Performance of Exercise Scheduled for 9007181990-05-17017 May 1990 Forwards Public Version of Vermont Yankee Nuclear Power Station Emergency Response Preparedness Exercise 1990. Exercise Scenario Package Includes All Info Pertinent to Performance of Exercise Scheduled for 900718 ML20042G9061990-05-10010 May 1990 Forwards Proprietary Supplemental Info to 900419 Response to NRC 900309 Ltr Re FROSSTEY-2 Fuel Performance Code.Info Withheld ML20042F6471990-05-0404 May 1990 Ack That NRC Will Issue Supplementary Info to NRC 900307 Request for Installation of Neutron Flux Monitoring Instrumentation That Conforms to Requirements of Reg Guide 1.97 & 10CFR50.49 at Plant ML20042E7291990-04-23023 April 1990 Forwards Pages Omitted from 900314 Revs 16-18 to Physical Security Plan.Revs Withheld ML20012F3511990-03-30030 March 1990 Provides Supplemental Response to Station Blackout Rule (10CFR50.63).Util Will Use Alternate Ac Power Source Available within 10 Minutes of Onset of Station Blackout to Meet Requirements of Station Blackout Rule ML20012D0301990-03-19019 March 1990 Forwards Response to Generic Ltr 89-19 Re Resolution of USI A-47.Feedwater Sys Trip Relays,Interfacing W/Feedwater Pump Control Circuitry,Powered from Supplies Originating from safety-related Dc Sources ML20012D0241990-03-16016 March 1990 Forwards Supplemental Info Re Feedwater Check Valve V28B Flaws Evaluation,Per NRC Request.Util Remains Committed to Replacement of Subj Valve During Upcoming 1990 Refueling Outage ML20012C6381990-03-15015 March 1990 Forwards Vermont Yankee Nuclear Power Corp Financial Statements 891231,1988 & 1987. ML20012C6071990-03-15015 March 1990 Forwards Method for Generation of One-Dimensional Kinetics Data for RETRAN-02, Per NUREG-0393 & 891211 Request ML20012B8311990-03-0909 March 1990 Forwards Proprietary Vermont Yankee Evaluation Model Sample Problem 0.7 Ft(2) Break in Recirculation Discharge Loop, in Response to 900208 Telcon.Rept Withheld (Ref 10CFR2.790) ML20012B6131990-03-0909 March 1990 Informs of Schedular Changes Made W/Regard to Plant Licensed Operator Requalification Training Program ML20006E8871990-02-15015 February 1990 Provides NRC W/Results of Licensee Review of Design Bases & Operability Status of torus-to-reactor Bldg Vacuum Breakers ML20011E6791990-02-0505 February 1990 Responds to Weaknesses Noted in SALP Rept 50-271/88-99 for Jul 1988 to Sept 1989.Implementation of Emergency Response Facility Info Sys Nearing Completion & Remaining Safety Class Vendor Manuals Will Be Completed During 1990 ML20006D1571990-02-0202 February 1990 Responds to 891226 Request for Addl Info Re YAEC-1683 on MICBURN-3/CASMO-3/TABLES-3/SIMULATE-3 Benchmarking.Hot Eigenvalue Std Deviation on Table 5.7 of YAEC-1683 Reduced to 0.00098 w/SIMULATE-3 ML20006B1351990-01-22022 January 1990 Forwards Responses to Generic Ltr 89-13 Re Svc Water Sys Problems Affecting safety-related Equipment.Establishment of Program Revs Prior to Startup from Next Refueling Outage, Scheduled for Fall 1990,planned ML20006A4441990-01-16016 January 1990 Forwards Revised Page 127 of Tech Specs to Clarify Proposed Change 134, Rev of Pressure Suppression - Reactor Bldg Vacuum Breaker Sys Operability Requirements. Change Involves Adoption of Language Consistent W/Bwr STS ML19354E8001990-01-16016 January 1990 Forwards Addl Info Re Testing of Cable Vault C02 Suppression Sys During 891031-1102,per NRC 890518 & 0821 Requests.Encl Final Test Rept Demonstrates That Carbon Dioxide Sys Will Satisfy Design Bases for Greater than 10 Minutes in Room ML20005G0841990-01-10010 January 1990 Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking of high-hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or Valves of Similar Design ML20005E8201990-01-0202 January 1990 Forwards Minutes of NRC 890907 Meeting W/Util in Rockville,Md Re Util LOCA Analysis Program.List of Attendees Also Encl ML20005F0551990-01-0202 January 1990 Informs That Util Has Implemented Fitness for Duty Program, in Compliance w/10CFR26 ML20005E3531989-12-28028 December 1989 Forwards Response to Generic Ltr 89-10 Re safety-related motor-operated Valve Testing & Surveillance.Util Intends to Extend Existing IE Bulletin 85-003 Program to Cover motor- Operated Valves within Scope of Ltr ML20005E3191989-12-28028 December 1989 Responds to Violations Noted in Insp Rept 50-271/89-17 on 890906-1016.Corrective Actions:Plant Procedures Revised & Addl Meetings Between Plant Manager,Dept Supervisors & Personnel to Take Place ML19332G1791989-12-12012 December 1989 Forwards Rev 0 to Vermont Yankee Nuclear Power Station Cycle 14 Core Operating Limits Rept. ML19332F2781989-11-30030 November 1989 Forwards Rev 1 to YAEC-1693, Application of One-Dimensional Kenetics to BWR Transient Analysis Methods, Per 891106 Ltr.Rept Presents Methodology,Verification & Justification for Application of RETRAN-02 One Dimensional Option ML19332E3511989-11-29029 November 1989 Forwards Annual Cashflow Statements for 1989 as Evidence of Util Maint of Approved Guarantee,Per Requirements of 10CFR140.21 Re Licensee Guarantees of Payment of Deferred Premiums ML19332E5281989-11-28028 November 1989 Requests Removal of Change B to Proposed Change 148 Re Rev to Pages 5b & 6a Correcting Administrative Error in Tech Spec 2.1 ML19332D3801989-11-22022 November 1989 Responds to NRC Generic Ltr 89-21 Re Request for Info Re Status of Implementation of USI Requirements.Encl Table Details Implementation Status for USIs for Which Final Technical Resolution Achieved ML19324C1501989-11-10010 November 1989 Responds to NRC Bulletin 88-010,Suppl 1 Re Molded Case Circuit Breakers.Program Initiated to Ensure That Breakers Can Perform Safety Functions ML19324C2201989-11-0606 November 1989 Requests Change in Review & Approval Basis from Facility Specific to Generic Because Methods Described in YAEC-1693 & YAEC-1694 Applicable to All BWRs ML19325F0261989-11-0606 November 1989 Responds to Generic Ltr 89-07, Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs. Util Has Evaluated Listed Considerations,Including Safe Standoff Distances for Vital Equipment ML19324B7431989-10-30030 October 1989 Responds to Generic Ltr 89-16 Re Installation of Hardened Wetwell Vent.Util Expects to Establish Specific Design Criteria to Install Enhanced Containment Overpressure Protection Capability by End of 1992 Refueling Outage ML19324B8481989-10-30030 October 1989 Provides NRC W/Test Acceptance Criteria for Alternate Test of CO2 Suppression Sys,Per 891025 Meeting.Ability to Contain CO2 at Appropriate Concentration for Required Duration,As Well as Ability to Withstand Dynamics of Discharge,Verified 1990-09-10
[Table view] |
Text
VE*RMONT YANKEE NUCLEAR POWER CORPORATION 7 Ferry Roao, Brattleboro, VT 05301 7002 BVY 90-007 ENGINE I OFFICE t 140 M AIN STREET BOLToN MA 01740 (500)779 6711 January 22, 1990 U.S. Nuclear Regulatory Commission Washington, D.C. 20556 Attention: Document Control Desk
References:
a) License No. OPR-28 (Docket No. S0-271) b) Letter, USNRC to All Holders of Operating Licenses or Construction Permits for Nuclear Power Plants, NVY 89-156, Generic Letter 89-13, dated 7/18/89 c) EPRI Interim Report, " Heat Exchanger Performance Monitoring Guidelines for Service Water Systems," by N. Stambaugh and W. Closser, dated July 1989 d) Letter, VYNPC to USNRC, BVY 89-76, Additional Response to Maintenance Team Inspection Report, dated 8/11/89
Dear Sir:
Subject:
Response to Generic Letter 89-13, Service Water System Problems Affecting Safety Related Equipment By letter dated July 18, 1989 (Reference b)], USNRC presented a number of recent operating events and studies that led USNRC to question licensee ;
compliance with General Design Criteria (GDC) that apply to station Service Water systems. As defined by 10CFR50, Appendix A, the three GDC of concern are: GDC i 44 - Cooling Water GDC 45 - Inspection of Cooling Water Systems and GDC 46 -
Testing of Cooling Water System, as they apply to Service Water systems.
To assure the above issues are being adequately addressed,-Generic Letter 3 89-13 provides a discussion of five recommended actions to be taken by licen-sees. A summary of each of those recommendations and the corresponding Vermont Yankee responses are included in Attachment A. In addition to the programs / practices currently in place to maintain Service Water system perfor-mance, further enhancements are included in Attachment A. These program revi-7 sions will be established prior to startup from the next refueling outage, currently scheduled for the fall of 1990. Per the reporting requirements of ((
this Generic Letter, a letter confirming implementation of these actions will be submitted within 30 days of such implementation, tj Based on the above, Vermont Yankee concludes that it has adequately addressed recommendations I through V of.this Generic Letter to continue to +
. assure the reliability / adequacy of the Service Water system. It should also be noted that this response provides a summary of our present Service Water system In the future, we expect that additional operating experience with efforts.
/
i:hese efforts may allow us to refine the practices discussed in this response. -
i g'g ,
9001310500 900122 \ e PDR ADOCK 05000271 .
P PDC
, VERMONT YANKEE NUCLEAR POWER CORPOR ATION U.S. Nuclear Regulatory Commission January 22, 1990 Page 2 We trust that the information contained in this letter is satisfactory however, should you have any questions or require additional information, please do not hesitate to contact us.
Very truly yours, VE MG T YANKEE NUCLEAR P WER CORPORATION
&- ,$ W *'
erren P. %rphy Vice President and Manager of Operations
)
/dm cci USNRC Region I Administrator ;
USNRC Resident Inspector, VYNPS l USNRC Project Manager, VYNPS l
l STATE OF VERMONT)
! )ss WINDHAM COUNTY )
Then personally appeared before n,e, Warren P. Murphy, who, being duly sworn, did stste that he is Vice President and Manager of Operations of Vermont Yankee Nuclear Power Corporation, that he is duly authorized to execute and file the foregoirig document in the name and on the behalf of Vermont Yankee Nuclear Power corporation and that the statements therein are true to the best of his knowledge and belief, b I e m 1. A w Diane M. McCue Notary Public My Commission Expires tebruar 991
. CCg f
5
.y%+ C03)lT%
r l
e T ATTACHMENT A l
SUMMARY
OF NRC RECOMMENDED ACTION I For open-cycle Service Watwr systems, implement and maintain an ongoing-program of surveillance and control techniques to significantly reduce the inci-dence of flow blockage events caused by biofouling.
pesoonse-In 1980, Vermont Yankee began an evaluation of the existing condition of the station Service Water system to identify methods for controlling / eliminating biofouling and corrosion of the system piping. This evaluation ef fort included the following actions:
a) Removal of small diameter (2%" and under) pipe samples to determine their condition, b) Internal inspection of large lines and heat exchangers.
c) Analysis of the existing corrosion product composition.
d) Installation of spool pieces and inspection / cleanout ports for system inspection and cleaning.
e) Initiation of an ultrasonic measurement program for surveillance of pipe wall thickness in various Service Water system locations.
f) Establishment of Pipe / Equipment Coating Testing.
Results of the above evaluation effort concluded that the Vermont Yankee Service Water system is susceptible to corrosion and that the corrosion is microbiologically induced by iron bacteria. These bacteria consume the carbon, steel piping material and produce large volume depositions on the pipe wall.
In an effort to control iron bacteria and to maintain acceptable Service.
Water system operation and capabilities, the following programs / practices were.
put into place.
o Service Water Piping Ultrasonic Thickness Measurement Program o Small Bore Pipe Replacement Program o Macroscopic Biological Fouling Species Surveillance I
A discussion of each of these programs / practices is given below.
)
- 1) Service Water Pipino Ultrasonic Thickness Measurement Prooram The Service Water Piping Ultrasonic (U.T.) Thickness Measurement Program was created in 1981 to allow monitoring of corrosion rates in the Service )
j Water system piping at Vermont Yankee.- A previous study had determined j i
- l
Attachment A Page 2 that system piping corrosion was caused by iron bacteria. The iron bac-teria consume the pipe wall and produce a hydrated iron oxide which has been found to occupy approximately ten times the volume of the original steel. This led to the thinning of pipe walls, the reduction of pipe inside diameter and, in some cases, clogging of small bore Service Water lines.
To quantify this pnenomena, Vermont Yankee initiated this program as part of a long-term coerosion control program. U.T. inspection grids were per-manently identified on Service Water lines at various locations to ensure measurement repeatability. Currently, twenty-seven (27) locations are being measured and evaluated once during each operating cycle. All loca- ,
tions measured are analyzed to ensure pipe minimum wall thickness will be :
maintained during plant operating life. General measurements have shown ;
wall thinning to be minor when compared to design code minimum wall j thickness standards. t Ultrasonic thickness testing has shown where the most serious pipe wall thinning / corrosion product build-up has occurred and has allowed the deter-mination of corrosion rates for corrective action determination. The U.T.
testing also allows evaluation of cor-' n control technique effec- ,
tiveness. '
4 The data that has been taken to data .onjunc+ ion with this program has shown that: {
i 4
a) all small bore (2.5" diame' under) lines on the Service Water system needed to be replaceo ensure that flow blockage would not j take place (see discussion of small bore pipe replacement below); and b) large size lines do not need to be replaced because pipe wall thinning has been determined by test results to essentially cease after approximately 0.05" of pipe wall thickness is consumed. Since 3
corrosion product build-up has been found to be approximately ten -
times the thickness of consumed material, a corrosion product build-up of 0.5" is expected in these locations. This has been confirmed by inspection. Since_these lines were originally designed'with excess capacity, this one inch of pipe diameter loss is negligible.
- 2) Small Bore Pipe Replacement Program 1 As discussed above, the initial phase of the corrosion control program at Vermont Yankee was a study of the corrosion build-up at various locations throughout the Service Water system. Once the corrosion was identified and the required information was gathered, a full scale replacement of small I bore carbon steel Service Water lines was initiated. Since the replacement l of the small bore piping has been completed, only one other location has required replacement due to the potential of clogging. It has been deter-mined by Vermont Yankee that all of the small bore carbon steel Service 3
~
a Attachment A Page 3 Water lines that were susceptible to corrosion product build-up have been replaced with either stainless steel or copper piping. Based on the above, it is concluded that flow blockage of small bore lines has.been adequately and completely addressed.
- 3) Macroscopic Bioloaical Foulino Species Surveillance Vermont Yankee has performed sampling to determine the presence of macroscopic biological fouling species (Asiatic clam) in the Service Water system source. No evidence of this species has been found to date.
To continue to assure the absence of macroscopic fouling organisms,. Vermont Yankee will perform water and substrate sampling annually to detect the presence of both Asiatic clams and Zebra mussels. (NOTE: Per NRC Information Notice No. 89-76, Zebra mussels have recently been found to be populating Great Lakes water sources.) If sampling detects their presence, system chlorination or an equally effective treatment program will be instituted.
SUMMARY
OF NRC RECOMMENDED ACTION II l i
Establish and implement an initial and periodic retest program to verify 1 that safety-related heat exchangers will meet their design / functional require- !
ments.
j
Response
The following is a list of all safety-related heat exchangers that transfer heat to an Ultimate Heat Sink as defined in this Generic Letter.
Residual Heat Removal (RHR) Heat Exchangers IA, 1B Reactor Building Closed Cooling Water Heat Exchangers IA, 18 Diesel Generator Jacket Cooler A, B ;
Diesel Generator Lube Oil Cooler A, B Diesel Generator After Cooler A, B j RHR Service Water Pump Motor Coolers IA, IB, 1C, ID Reactor Building Recirculation Units (RRU) E. 6,7,8 Cooling Tower #2 Cell #1 In responding to this issue, Vermont Yankee has reviewed an EPRI Interim Report released in July 1989 entitled " Heat Exchanger Performance Monitoring ,
Guidelines for Service Water Systems" [ Reference c)). -This document provides a ~j number of heat exchanger performance monitoring options to assure heat i exchangers will meet their intended safety functions. 4 Vermont Yankee has concluded that the majority of the heat exchangers !
listed above are already included in existing equipment monitoring programs that !
coincide with EPRI interim report guidelines. Only the four Reactor Recirculation Units and the four RHR/SW Motor Coolers will need to be added to these programs.
i
' Attachment A Page 4 i
A discussion of current and proposed monitoring methods for the subject heat exchangers is given below. This combination of testing, preventive main-tenance, differential pressure monitoring and temperature monitoring will ensure ,
continued equipment capability. '
a) Heat Transfer Method +
The " Heat Transfer Method" of performance monitoring consists of measuring heat exchanger stream temperatures and flows while a substantial heat load is being applied. This data is then used to directly determine heat.
exchanger heat transfer capability. This method is described in more detail in section 4.1 and 5.0 of the EPRI Interim Report (Reference c)].
- 1. Residual Heat Removal (E-14-1A, IB)
The two RHR heat exchangers were inspected, cleaned and eddy current tested during the 1989 refueling outage. They will be tested by measuring their heat transfer capability as discussed above during'the 1990 refueling outage. This testing will again be performed during the two subsequent refueling outages. Based on this data, a t4ssting frequency will be determined to provide assurance that the design heat r removal capability of these heat exchangers is maintained.
b) Periodic Maintenance Method The " Periodic Maintenance" method of performance monitoring consists of visually inspecting the heat exchangers with the use of a fiber scope or by disassembly. If the visual inspection reveals that fouling is present, the
, heat exchanger is physically cleaned. This method is described in more l
detail in sections 4.5 and 9.0 of the EPRI Interim Report [ Reference c)].
In addition to inspecting and cleaning of the heat exchangers, eddy current testing is performed to identify tube wall thinning.
- 1. Reactor Building Closed Cooling Water (E-8-1A, IB)
Both RBCCW heat exchaners were eddy current tested and cleaned in 1981, 1985 and 1989. Based on the findings of those inspections, the ,
RBCCW heat exchangers are now scheduled to be cleaned once every
~
operating cycle.
- 2. Diesel Generator Jacket, Lube Oil & After Cooler A, B The Service Water supplied cooling system of each diesel generator is made up of three heat exchangers. 'The three coolers are the Jacket,
- Lube Oil and After Coolers. All three coolers in.both diesel genera-l tors have been inspected and eddy current tested. It was determined from these inspections that no significant fouling or corrosion was present and no follow-up cleaning was required.
Attachment A Page 5 To continue to ensure the cleanliness of these heat exchangers, all ;
six (three per diesel generator) will be inspected and cleaned as necessary when preventive maintenance overhaul is performed on the-diesel generators.
- 3. Cooling Tower #2 Cell #1 '
Vermont Yankee uses two-eleven cell cross vent cooling towers to cool- .
the Circulating and Service Water systems during the summer months.
- The first cell in-the West Cooling Tower (Cooling Tower #2) is con-sidered to be safety class 2 and is-seismically qualified. Thislis because this cell is part of the Alternate Cooling system, which would '
be used if the normal Service Water system suction source was-lost.
Vermont Yankee visually inspects all of the cooling tower cells on an annual basis. -If required, maintenance is performed at that time.
In addition, the deep basin area under Cooling Tower #2 is visually inspected by divers during every refueling outage. If it is deter-mined necessary, the deep basin is drained and cleaned to remove excess silt. This inspection ensures that the function of the safety class cooling tower cell is maintained.
c) Temperature Monitorino Method 1
The Temperature Monitoring Method consists of monitoring the temperature of the component that is being cooled by the corresponding heat exchanger.
This method is described in more detail in sections 4.3 and 7.0 of the EPRI-Interim Report [ Reference c)].
- 1. RHR/SW Pump Motor Cooling P8-1A, IB, 10, ID (water / oil)
Performance monitoring of the RHR/SW Pump Motor Coolers will be insti-tuted using the Temperature Monitoring method. -This method will con-sist of monitoring the pump motor temperature during monthly pump surveillances. If the pump motor temperature rises above an appropriate limit, action will be taken. This monitoring program will ;
be initiated prior to the end of the,next refueling outage, j d) Delta P Method j i
The Delta P Method, as described in section 4.2 and 6.0 of the EPRI Interim i Report (Reference c)] allows monitoring of heat exchanger fouling. l Monitoring is accomplished by correlating heat exchanger flow rates and '
corresponding pressure drops, i l
1 l
l $
Attachment A Page 6
- 1. Reactor Recirculation Units 5, 6, 7, 8 (water / air)
The performance of the four safety-related RRU units that cool.the RHR ;
corner rooms will be evaluated by measuring the inlet and outlet pressures as well as the Service Water flow rate. If the flow rate and pressures are comparable to the design values, the unit will be considered to be free of fouling. This monitoring program will be initiated prior to end of the next refueling outage,. which is currently scheduled for the fall of 1990. 7 e) Closed Cvele Heat Exchanoers At Vermont Yankee, closed cooling water systems are chemically treated to prevent corrosion of system components. The chemicals consist of either molybdate-based caustic passivators or filming-type corrosion inhibitors.
The adequacy of this treatment program was recently evaluated as part of an internal INPO commitment. The treatment of these systems currently meets or exceeds industry standards and vendor recommendations. No changes in closed cooling water chemical treatment programs. are necessary.
SUMMARY
OF NRC RECOMMENDED ACTION III Establish a routine inspection and maintenance program 'which will ensure that the performance of safety-related systems serviced by the SW system will not degrade due to corrosion, erosion, protective coating failure, silting and biofouling in the SW system. Maintenance should include at.least the removal of excessive accumulations of biofouling agents,. corrosion products and silt and the repair of defective coatings and corroded parts which may affect safety system performance. ,
Response
A number of programs are currently in place at Vermont Yankee that actively-pursue the identification and repair / resolution of the concerns listed in this item. As discussed in the response to Recommended Action I above,- piping corro-sion concerns have been thoroughly addressed by small bore piping replacement and the ongoing pipe wall thickness surveillance program. The biofouling issue has also been addressed by that program and by the heat exchanger maintenance /
monitoring methods described in the response to Recommended Action II.
To further assure Service Water system reliability, the following main-tenance programs / practices are currently.in place at Vermont Yankee.
a) Check Valve Preventive Maintenance Proaram This program was internally initiated and then further refined to include input from INPO SOER 86-03, " Check Valve Failures and Degradations".
' Service Water system check valves identified in the program are totally disassembled and inspected per a visual inspection checklist. -This-checklist allows documentation and evaluation of numerous items important
Attachment A Page 7 i
I to proper check valve operation. These items include, but are not limited to, valve body and seat condition, disc condition, hinge pin diameter and condition. All check valves in this program are then refurbished, as required, after inspection. Inspection results are used to establish future inspection frequency.
b) Heat Exchanaer Eddy Current Testina Program This program covers inspection of Service Water system heat exchanger tubing for evidence of pitting, erosion, corrosion, and excessive sludge build-up. Tubing is then mechanically cleaned and deposits removed. After each inspection, an evaluation is performed using the data obtained and past inspection results to validate / revise the inspection frequency.
c) Service Water Intake Structure Cleanino The structure and traveling screen filtration' systems are inspected by divers once per operating cycle. Any debris or obstructions are removed to assure a reliable Service Water pump suction path, d) Service Water Pump Maintenance Each of the four Service Water pumps is inspected and overhauled on a bien-nial basis. In addition, all pumps are tested on a monthly basis per the-ASME Section XI Inservice Testing Program.
e) Service Water Strainer Maintenance Strainers on the Service Water pump discharge are monitored for changes in differential pressure and are cleaned as indicated by those changes, f) Service Water Valve Inspection Procram The Service Water Valve Inspection Program was initiated.in 1982 and is being further refined by Vermont Yankee. During the 1990 refueling outage, this program will institute a long-range schedule for taking Service Water.
valves out of service, disassembling the valves for inspection and repairing as required. It should be noted that protective coatings have been applied to a small number-of Service Water system valves and their condition is being monitored via the Valve Inspection Program. Protective coatings are not in use in Vermont Yankee safety class Service Water piping.
In addition to the above, locations in the Service Water system that may be susceptiole to erosion and siiting will be identified as described in the <
response to Recommended Action IV below. Appropriate inspection of these loca-tions will then be performed so that corrective action can be taken. .
Attachment A- >
Page 8
SUMMARY
OF NRC RECOMMENDED ACTION IV Confirm that the as-built SW system meets its design requirements'and w'ill perform its intended function in accordance with the applicable licensing basis of the plant; including confirmation of its ability to perform its-required safety function in the event of a single active component failure.
Response
Through the Design Change process, Vermont Yankee adequately maintains the Plant Licensing Basis as set forth in the Final Safety Analysis Report, Technical Specifications, and the Design Basis Manual. Implicit in this process is the evaluation of single active component failures. ~To further ensure the functional adequacy of the Service Water system, a computerized system flow model is being developed. This model will also be used to determine system locations susceptible to erosion or silting based on fluid stream velocities.-
Based on an evaluation of the results from the completed flow model, an action plan addressing any further efforts needed on this issue will be developed in the fall of 1990 with an appropriate schedule.
SUMMARY
OF NRC RECOMMENDED ACTION V Establish and implement maintenance practices, operating procedures and effective training programs which will ensure that safety-related equipment cooled by the SW system will perform its intended function and-that plant staff responsible for this equipment will reduce the-incidence of human errors- that-frequently occur in the operation, repair and maintenance of SW systems.
t
Response
At Vermont Yankee, the~ maintenance and operation'of the Service Water-system is closely controlled by operating and surveillance procedures. All of i
these procedures are required to be comprehensively reviewed on a biennial basis. At a minimum, this biennial review includes:
a) a review of all procedure steps; b) verification of references; and c) identification of the impact of any proposed changes in other procedures. '
! Based on the above, Vermont Yankee believes that the procedures that control the maintenance and operation of the Service Water system are adequately
- reviewed. Procedure changes required to' implement responses given to this 1
Generic Letter will be in place prior to the end of the 1990 refueling outage.
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In addition, plant operations personnel have received enhanced training on l
the issues raised by this Generic Letter. This training promoted an increased I
awareness of Service Water system susceptibilities as discussed in the NRC Recommended Actions and the programs and practices in place at Vermont Yankee to >
address them. This training was completed in the fall of'1989.
As described in Reference d), Vermont' Yankee has recently developed a main-tenance program document to assure that good maintenance activities continue in I the future for all plant equipment. This document is intended to establish additional maintenance programmatic controls and to formalize current main-tenance good practices. '
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