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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] |
Text
. . . . - - . . . . - . . . - . .- . - .
l t,
VERMONT- YANKEE NUCLEAR POWER CORPORATION ]
i
. Ferry Road, Brattleboro. VT 05301-7002
,$ l
.t January 14, 1997 l BVY 97-7 :
TDL 97-001
<so2> 257-san United States Nuclear Regulatory Commission- ' '
ATTN: Document Control Desk Washington, DC 20555
~
Reference:
(a) License No. DPR-28 (Docket No. 50-271)
Subject:
Requested Testing Abstracts for Vermont Yankee Simulator Upgrades ,
As discussed per our phone conversation of December 18, 1996, enclosed are the Vermont Yankee Discrepancy Reports and Test Abstracts for the following Simulator Upgrade Projects: ;
Encore to PC conversion, Core and Thermal Hydraulics l Attachment 1 DR #94-0194 and DR #94-0181 ..
I Attachment 2 Primary Containment !
DR #91-0068 Attachment 3 Secondary Containment !
DR #93-0003 If you require any further information or have any questions regarding these upgrade projects, ,
please call me at (802) 258-4144.
, I 1
Sincerely, VERMONT YANKEE NUCLEAR POWER CORPORATION I r Mark)R. Krider k Training Support Supervisor Enclosures 9N1220295970114M ApocK 0500o271 i
POR p P PDRL c: USNRC Regional Administrator, Region I j
..USNRC Resident Inspector. - VYNPS l
. USNRC Project Manager - VYNPS j
- USNRC Frank Collins, Operator Examiner .j i
t
ATTACHMENT 1
'dy
,. VERMONT YANKEE SIMULATOR DISCREPANCY REPORT 94-0194 TITLE: CONVERT SOFTWARE FROM ENCORE TO PENTIUM STATE OF SIMULATOR:
REFERENCE:
DESIGN CHANGE:
IC:
TEST:
DISCREPANCY DESCRIPTION:
Convert all Simulator modules from Encore to Pentium platform.
EXPECTED RESULTS:
Simulator operate identically after conversion as before.
- SHEETS DATEl ATTACHED ORIGINATOR: JOHN T. HUDACHEK 12/20/94 0 COGNIZANT ENGINEER: JOHN T. HUDACHEK 12/20/94 0 HARDWARE ENGINEER:
FIDELITY ASSESSOR: DAVID E. TUTTLE 12/20/94 0 PRIORITY: Medium DUE DATE:
VALID DR: Yes JOHN T. HUDACHEK DATE: 02/13/96 COST JUSTIFIED:Yes JOHN T. HUDACHEK DATE: 02/13/96 WORK COMPLETED: JOHN T. HUDACHEK DATE- 02/13/96 DRAWINGS: None DOCUMENTA ON 'D HN .
QDACHEK DATE: 02/14/96 TESTED: m.ev- cv/ i DATE: 02/16/96 DAVID E. TUTTLE CLOSED: M }. DATE: 02/16/96 JOHN T. HUDACHEK w.
I
. ATTACHMENT 1 D3,screpancy" Report 94-0194 Page 5 of 6 Originated by:JTHU 12/20/94
Title:
CONVERT SOFTWARE FROM ENCORE TO PENTIUM CE:JTHU HE: FA:DET Acceptance Test
- 1. SUCCESFUL COMPLETION OF ALL ANSI REQUIRED TESTS (ALL MALFUNCTIONS TO BE TESTED)
o ATTACHMENT 1 VERMONT YANKEE SIMULATOR DISCREPANCY REPORT 94-0181 TITLE: CORE & THERMAL HYDRAULICS UPGRADE STATE OF SIMULATOR:.
REFERENCE:
APRIL 13, 1994 SPECIFICATION DESIGN CHANGE:
IC:
TEST:
DISCREPANCY DESCRIPTION:
Replace current core & thermal hydraulics modes with state-of-the -art advanced 3-D, multinodal, fully dynamic models.
EXPECTED RESULTS:
See April 13, 1994 Specification.
- SHEETS DATEl ATTACHED ORIGINATOR: JOHN T. HUDACHEK 11/14/94 0 COGNIZANT ENGINEER: JOHN T. HUDACHEK 11/14/94 0 HARDWARE ENGINEER:
FIDELITY ASSESSOR: DAVID E. TUTTLE 11/14/94 0 PRIORITY: Medium DUE DATE:
VALID DR: Yes JOHN T. HUDACHEK DATE: 11/14/94 COST JUSTIFIED:Yes JOHN T. HUDACHEK DATE: 11/14/94 WORK COMPLETED: JOHN T. HUDACHEK DATE: 02/13/96 DRAWINGS: N na s DOCUMENTA ON NE: OHN T. HUDACHEK DATE: 02/13/96 TESTED: #
2n 3v I) DATE: 02/16/96 DAVID E. TUTTLE g CLOSED: M T. -8^s DATE: 02/16/96 JOHN T. HUDACHEK
ATTACHMENT 1 Discrepncy' Report 94-0181 Page 5 of 6 Originated by:JTHU 11/14/94
Title:
CORE & THERMAL HYDRAULICS UPGRADE CE:JTHU HE: FA:DET Acceptance Test
- 1. PERFORM SUCCESFUL STARTUP AND SHUTDOWN OF SIMULATOR USING VY OP'S
- 2. PERFORM SUCCESFUL SCRAM AND RECOVERY USING VY OP'S
- 3. PERFORM SUCCESFULLY ANSI REQUIRED TRANSIENT TESTING
- 4. INSURE SIMULATOR RUNS IN REAL TIME WITH CORE / THERMAL MODELS INSTALLED l
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YERMONT YANKEE PLANT SIMULATOR UPGRADE PERFORMANCE TESTING ATTACHMENT 1 ,
l The following tests were performed using simulator procedure SIM-371, Simulator- 1 Performance Testing with the new operating environment, reactor core and thermal i hydraulics models fully integrated:
- 1. ANSUANS 3.5 Bl.1 Startup, Shutdown and Steady State Tests
- a. Startup from cold to rated power
- b. Shutdown to cold conditions from rated power
- c. Recovery from plant Scram to rated power l
- d. Critical (Heat Balance) and non-critical data comparisons at three power levels
- e. One hour stability test
- 2. ANSI /ANS 3.5 3.1.1 Normal Plant Evolutions l
- a. Safety Related Systems Surveillance ,
- 3. ANSUANS 3.5 4.3 Simulator Operating Limits
- a. Simulator Out of Limits Test
- 4. ANSI /ANS 3.5 bl.2 Transient Performance Tests
- a. ANSI Bl.2(1) Manual Scram >
- b. ANSI Bl.2(2) Simultaneous Trip Of All Feedwater Pumps
- c. ANSI Bl.2(3) Simultaneous Closure Of All Main Steam Isolation Valves
.d. ANSI Bl.2(4) Simultaneous Trip Of All Recirc Pumps
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I VERMONT YANKEE PLANT SIMULATOR ,
UPGRADE PERFORMANCE TESTING ATTACHMENT 1 (Continued)
- e. ANSI Bl.2(5) Single Recirculation Pump Trip
- f. -ANSI Bl.2(6) Main Turbine Trip 1 r
- g. ANSI Bl.2(7) Maximum Rate Power Ramp f
- h. ANSI Bl.2(8) Reactor Coolant System Rupture
- i. ANSI Bl.2(9) Maximum Unisolable Main Steam Line Rupture
.j. ANSI Bl.2(10) Simultaneous Closure of All Main Steam Isolation Valves with a Stuck Open Safety Relief Valve
- 5. Computer Real Time Verification 'i
- 6. ANSI /ANS 3.5 A3.4 Malfunction Tests a All malfunctions were retested.
I Open item upgrade performance testing failures remaining as of this submittal.
None i
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' ATTACHMENT 2
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VERMONT YANKEE SIMULATOR DISCREPANCY REPORT 91-0068 TITLE: NEW CONTAINMENT MODEL
-STATE OF SIMULATOR:
REFERENCE:
DESIGN CIWIGE:
IC:
TEST:
DISCREPANCY DESCRIPTION:
DR 88-0178 89-0224 89-0101 AND GENERAL CONTAINMENT RESPONSE REQUIRE AN UPGRADE TO THE PRESENT CONTAINMENT MODEL EXPECTED RESULTS:
NEW CONTAINMENT MODEL
- SHEETS DATEl ATTACHED ORIGINATOR: DAVID E. TUTTLE 04/05/91 0 COGNIZANT ENGINEER: DAVID E. TUTTLE 04/05/91 0 HARDWARE ENGINEER: I FIDELITY ASSESSOR: MARK R. KRIDER 04/05/91 0 ;
PRIORITY: Medium DUE DATE:
VALID DR: Yes DAVID E. TUTTLE DATE: 03/30/92 COST JUSTIFIED:Yes JOHN T. HUDACHEK DATE: 03/30/92
WORK COMPLETED: DAVID E. TUTTLE DATE: 03/30/92 DRAWINGS: None DOCUMENTATION DONE: DAVID E. TUTTLE DATE: 03/30/92
-TESTED: 9~
DATE: 04/07/92 MARK R. KRIDER
- CLOSED: T JOHN lh[a e T. HUDACHEK DATE: 04/07/92
ATTACHMENT 2 Discrepancy Report- 91-0068 Page 5 of 6 Originated by:DET 04/05/91
Title:
NEW CONTAINMENT MODEL CE:DET HE: FA:MRK Acceptance Test NEW CONTAINMENT MODEL TESTED AND EXCEPTED USING CONTAINMENT MODEL ACCEPT ANCE TEST AFTER INSTALLATION BY GPI.
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ATTACHMENT 2 VERMONT YANKEE CONTAINMENT MODEL ACCEPTANCE TEST ,
INITIAL CONDITIONS
- 1. Unless specified elsewhere the simulator will be reset to IC-09 and left in freeze. ,
- 2. All malfunctions will be entered with a 1 min time delay.
DATA COLLECTION
- 1. Data will be collected for trending via "ANSISAVE" data set 3,
- 2. Data may also be collected from visual indication in the Simulator (charts indicators etc.).
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- 3. Data may be momtored using ISD.
ACCEPTANCE CRITERIA Results of tests will compare favorably with:
- 1. Benchmark Analysis of the Vermont Yankee Simulator performed by YAEC.
- 2. Plant data wlere applicable.
- 3. Best estimate when no data is available.
- 4. Simulation responds to normal operations in accordance with Vermont Yankee operating procedures and practices.
ACCEPTANCE TESTS A lARGE BREAK LOCA
- 1. Insert malf RROI A at 100% severity and place simulator to run.
- 2. Allow the simulator to run until ANSISAVE returns to the TSM prompt.
note: the simulator may be allowed to run longer to identify any adverse trends or indications.
- 3. Collect and analyze data.
B. UNISOLATABLE MAIN STEAMUNEl.EAK
- 1. Insert malf MS06 at 100% severity and place simulator to run.
- 2. Allow the simulator to run until ANSISAVE returns to the TSM prompt.
note: the simulator may be allowed to run longer to identify any adverse trends or indications.
- 3. Collect and analyze data.
-- . -. . - - - . - . . ~ . . . - -- . .- - . ..
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ATTACHMENT 2
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i C. SMALLBEAK LOCA l i
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- 1. Insert malf RROIB at 10% severity and place simulator to run. !
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- 2. Allow the simulator to run until ANSISAVE returns to the TSM prompt. :
note: the simulator may be allowed to run longer to identify any adverse trends or :
indications. l
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- 3. Collect and analyze data.
D. DBALOCAWITHLOSCOFPWR
- 1. Insert malf ED17 & RROI A at 100% and place simulator to run. #
' 2. Allow the simulator to run until ANSISAVE returns to the TSM prompt !
6 note: the simulator may be allowed to run longer to identify any adverse trends or )
indications. i
- 3. Collect and analpe data.
E. LOSS OFDRYWE11 COOLER !
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- 1. Insert malf PCO3D and place simulator to run.
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- 2. Allow the simulator to run until ANSISAVE returns to the TSM prompt.
r note: the simulator may be allowed to run longer to identify any adverse trerds or indications. T
- 3. Coll xt and analyze data.
F. LOSS OF DRYWELLCOOLERS
- 1. Insert malf PC03A.
la. Insert malf PCO3C on 5 min delay and place simulator to run.
- 2. Allow the simulator to run until ANSISAVE returns to the TSM prompt. ;
note: the simulator may be allowed to run longer to identify any adverse trends or indications.
- 3. Collect and analyze data. .
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ATTACHMENT 2 3
- 0. NODALTEMPERATURERESPON8E
' l. Plaz simulator to run.
- 2. Using the following malfunctions at low severity verify nodal temperature effects.
la. RR01A lb. RR01B Ic. MS06 id. AD01A Ic. AD01B If. AD01C Ig. AD01D note: initial effects should be seen in the node corresponding to the area the leak is located in and propagate into surrounding nodes in a timely manner.
i H. DRMEllDENERTKNPURGE
- 1. Place simulator to run. l
- 2. Using applicable VY procedures perform the steps necessary to deinert and purge the drywell. -
- 3. Insure no adverse temperature / pressure effects occur.
- 4. Insure procedure steps can be completed in a time frame comparable to plant data.
- 5. Insure torus level indication responds in a manner similar to referenced plant (OP 2115 fig.
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- 1. DRME111NERT10N
- 1. Reset simulator to IC-07 and run.
- 2. Using applicable VY procedures perf9rm the steps necessary to inert the dr3well. !
- 3. Insure no adverse temperature / pressure effects occur.
- 4. Insure procedure steps can be completed in a time frame comparable to plant data. )
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- 5. Insure torus level indication responds in a manner similar to refere:x:cd plant (OP 2115 fig.
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ATTACHMENT 2 J. FPCIFRLFLOWSURVELIANCETEST
- 1. Place simulator to run.
- 2. Using applicable VY procedures perform the steps necessary to complete the HPCI sury.
- 3. Insure containment temperature response compare favorably to plant sury, data.
K. DRYWELL SUMPSLEVELCECK
- 1. Reset simulator to IC02.
- 2. .
Insert malf FW21 at 1% and place simulator to run, note: malf severity may adjusted to insure accurate results are obtained.
- 3. Via ISD monitor the following:
- a. DWFDS level response
- b. DWEDS level response
- c. Dnwelllevel response
- d. Torus level response
- c. Drywell temp and press response
- f. Torus temp and press response
- 4. Test to continue until liquid level in Drywell overflows into Torus as evidenced by increase in Torus level with a halt in Drywell level increase.
L DRYWELL SPRAY NTIATION (LIQUID BREAK)
- 1. Insert malfs RR01 A.HP01,RC01,CD01 A-C,RH07A-B and place simulator to run.
- 2. After drywell press has increase above 20psig initiate dnvell spray sia "A" RHR loop
- 3. Monitor drywell temp and press response from panel indications.
M. DRYWELL SPRAY NTIATION (STEAM BREAK)
- 1. Insert malfs MS06,HP01,RC01,CD01 A-C,RH07A-B and palce simulator to run.
- 2. Aller drywell press has increase above 20psig initiate dowell spray sia "A" RHR loop
- 3. Monitor dnwell temp and press response from panel indications.
-ATTACHMENI2 N. FEEDWATER BAFAKINSIDE DRYWEli l.- Insert malf FW27A and place simulator to run.
- 2. Allow the simulator to run until ANSISAVE returns to the TSM prompt.
note: the simulator may be allowed to run longer to identify any adverse trends or indications.
- 3. Collect and analyze data.
O. CONTAMAENTFLOODNG(NO POVER)
- 1. Reset simulator to IC-02
- 2. Insert malf RROI A place simulator to run.
- 3. Allow simulator to run until drywell is flooded to T F or higher.
- 4. Monitor panel indications insuring no adverse Containment temp or press effects.
i P. CONTAMAENT FLOODNG FULLPOWER)
- 1. Insert malf RR01 A place simulator to run.
- 2. Allow simulator to run until drywell is flooded to TAF or higher.
- 3. Monitor panel indications insuring no adverse Containment temp or press effects.
Q. CONTAMAENT GAS MO PARTICULATE RAD MONITOR
- 1. Insert malf RX01 at .05% and place simulator to run.
- 2. Insure gas and particulate rad monitor responds to increase dr>well actisity.
R MODELSTRESSTESTFORWANTOFANAME)
- 1. Insert nulf RD12A/B (atws) and RR01B and place simulator to run.
- 2. Maintain this condition for I hr.
- 3. Insure simulator model doesn't cause an abort or computer fault.
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- ATTACHMENT 3
' VERMONT YANKEE SIMULATOR DISCREPANCY REPORT 93-0003 ;
i TITLE: NEW SECONDARY CONTAINMENT MODEL STATE OF SIMULATOR:
REFERENCE:
- DESIGN CHANGE: :
IC:
TEST:
DISCREPANCY DESCRIPTION:
THE.PRESENT SECONDARY MODEL IS INADEQUATE FOR THE LATEST TRAINING REQUIREMENTS EXPECTED RESULTS:
A NEW IMPROVED MODEL
- SHEETS DATEl ATTACHED ORIGINATOR: DAVID E. TUTTLE 01/08/93 0 COGNIZANT ENGINEER: DAVID E. TUTTLE 01/08/93 0 HARDWARE ENGINEER:
FIDELITY ASSESSOR: ALLEN F. THOMAS 01/08/93 0 PRIORITY: Medium DUE DATE:
VALID DR: Yes DAVID E. TUTTLE DATE: 06/02/93 COST JUSTIFIED:Yes JOHN T. HUDACHEK DATE: 06/02/93 WORK COMPLETED: DAVID E. TUTTLE DATE: 06/07/93 r DRAWINGS: None DOCUMENTATION- O $: DV E. TUTTLE DATE: 06/07/93 TESTED: ~
ft )Wud DATE: 08/27/93 tALLEN F. THOMAS CLOSED: / e 'e DATE: 09/08/93 JOHN T. HUDACHEK 3
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ATTACHMENT 3 Discrepancy Report 93-0003 Page 5 of 6 Originated by:DET 01/08/93
Title:
NEW SECONDARY CONTAINMENT MODEL CE:DET HE: FA: AFT Acceptance Test
- 1. THE ACCEPTANCE TEST FOR THIS DR WAS COMPLETED PRIOR TO ACCEPTANCE FROM GENERAL PHYSICS. THIS TEST IS AVAILABLE ON THE CORPORATE VAX DISK 3[SIM. THOMAS]SECONDARYCONTAINMENT.
- 2. INDIVIDUAL DR'S MAY STILL BE WRITTEN IF FOUND.
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. . ATTACHMENT 3 VERMONT YANKEE SECONDARY CONTAINMENT ACCElrrANCE TEST l l
I. STABILITY RUN. 1 INITIAL COiGITIONS:
i RESET TO IC-19.
PUT SIMULATOR IN RUN AND LET RUN FOR AN ONE(1) HOUR.
ACCEPTANCE CRITERIA: '
OBSERVE NO UNEXPECTED ALARMS OR CONDITIONS OCCURED. ;
II. REACTOR BUILDING VENTILATION l INITIAL CONDITIONS: '
RESET TO IC-19.
1 INPUT IDA P_CEM (RX BLDG VENT) TO 'OFF'.
4 ACCEPTANCE CRITERIA:
1 OBSERVE THRU ISD TEMPERTURE IN THE NODES INCREASED
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INITIAL CONDITIONS:
RESET TO IC-19.
INPUT IDA ECE22 (RRU-5 RHRSW PUMP AREA SW-23) TO 'OFF' STARTED RHRSW PUMPS , J ACCEPTANCE CRITERIA:
OBSERVE THRU ISD THAT TEMPERATURES IN NODES INCREASED III. MALFUNCTION TESTING l A. INITIAL CONDITION:
- RESET TO IC-19.
INPUT MALF. _C1102 (RWCU NON-REGEN. HEAT EXCH. LEAK) @l00%
FOR 120 SECONDS. ;
ACCEPTANCE CRITERIA:
RBCCW SURGE TANK INCREASE
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, ATTACHMENT 3 i B. INITIAL CONDITIONS:
RESET TO IC-19 INPUT MALF. CJJSl(RWCU LEAK UPSTREAM OF REGEN. HEAT EXCH.)
@l00% FOR 120 SECONDS.
ACCEPTANCE CRITERIA:
- RB VENT. RAD ALARM INCREASE RB VENT. FANS TRIP RB TEMPERATURE INCREASE RB/ CONT. GAS /PART INCREASE C. INITIAL CONDITIONS
RESET TO IC-19 INPUT MALF. _C1106(LINE BREAK IN RWCU PUMP B ROOM) @l00% FOR 120 SEC.
ACCEPTANCE CRITERIA:
RB VENT. FANS TRIP RB VENT. RAD ALARM INCREASE RB TEMPERATURE INCREASE D. INITIAL CONDITIONS:
RESET TO IC-19.
INPUT MALF. S_W_06 (RBCCW SYSTEM HEADER LEAK) @l00% FOR 120 SEC.
ACCEPTANCE CRITERIA:
RBCCW SURGE TANK DECREASE RB BLDG FLOOR AND EQUIPMENT DRAINS INCREASE E. INITIAL CONDITIONS:
RESET TO IC-19.
INPUT MALF. SWOSA/B (RBCCW HEAT F'{CH TUBE LEAK) @l00% FOR 120 SECONDS.
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M r .sh. 4 A ATTACHMENT 3 l l
l ACCEPTANCE CRITERIA: 1 RBCCW SURGE TANK INCREASE l
RB FLOOR AND EQUIP. DRAIN SUMPS INCREASE F. INITIAL CONDITIONS:
RESET TO IC-19.
INPUT MALF. fiW.Qi(RBCCW SURGE TANK MAKEUP VALVE FAILURE)
@l00%. ,
ACCEPTANCE CRITERIA: j RBCCW SURGE TANK LEVEL INCREASE RB FLOOR DRAIN SUMP INCREASE G. INITIAL CONDITION:
RESET TO IC-19. ,
INPUT MALF. IIEQ6 (HPCI EXH. DIAPHRAM FAILURE)
RUN HPCI FULL FLOW TEST -
ACCEPTANCE CRITERIA:
RB VENT. FAN ISOLATE RB VENT. RAD INCREASE ARM'S INCREASE RB TEMPERATURES INCREASE II. INITIAL CONDITIONS:
RESET TO IC-19.
INPUT MALF. lif.ll (HPCI STEAM LEAK AFTER V23-14)
RUN IIPCI FULL FLOW TEST ACCEPTANCE CRITERIA:
RB FANS ISOLATE RB VENT. RAD INCREASE ARM'S INCREASE RB TEMPERATURE INCREASE I
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-.- ' ATTACHMENT 3 i I. INITIAL CONDITIONS:
RESET TO IC-19.
INPUT MALF. RCDfi(RCIC EXH DIAPHRAGM FAILURE) j RUN RCIC FULL FLOW TEST f ACCEPTANCE CRITERIA: :
i RB FANS ISOLATE ARM'S INCREASE RB VENT. RAD INCRASE ;
J. INITIAL CONDITIONS: '
RESET TO IC-19.
INPUT MALF. RCD 2 (RCIC STEAM LEAK AFTER V13-131) [
RUN RCIC FULL FLOW TEST ACCEPTANCE CRITERIA: :
RB FANS ISOLATE RB VENT. RAD INCREASE i ARM'S INCREASE ;
K. INITIAL CONDITIONS:
RF3ET TO IC-19.
t INPUT MALF. EC10 (SUPPESSION POOL LEAK) @l00%
ACCEPTANCE CRITERIA:
RB EQUIP / FLOOR DRAINS INCREASE i L. INITIAL CONDITIONS: ;
RESET TO IC-19.
INPUT MALF. ECDfi(PRIMARY CONTAINMENT RUPTURE) @l00%.
ACCEPTANCE CRITERIA:
RB FANS ISOLATE RB VENT. RAD INCREASE CONT AIR MONITOR PART. INCREASE ARM'S INCREASE I
ATTACHMENT 3 M. INITIAL CONDITIONS:
RESET TO IC-19.
INPUT MALF. ECD 1(SECONDARY CONTAINMENT RUPTURE)
ACCEPTANCE CRITERIA:
LOST OF RX BLDG D/P N. INITIAL CONDITIONS:
RESET IC-19.
INPUT MALF. ECQL (FUEL POOL COOLING SYSTEM LEAK) @l00%.
ACCEPTANCE CRITERIA:
RB FANS ISOLATE ARM'S INCREASE RB FLOOR / EQUIP DRAIN SUMPS INCREASE 1
O. INITIAL CONDITIONS:
RESET IC-19.
INPUT MALF. MS91(MS LINE 'B' RUPTURE IN STEAM TUNNEL) @l00%
FOR 120 SECONDS.
ACCEPTANCE CRITERIA:
ARM'S INCREASE RB TEMPERATURE INCREASE RB VENT. RAD INCREASE RB FANS ISOLATE P. INITIAL CONDITIONS:
RESET IC-19.
INPUT MALF. RD18A/B (SCRAM DISCH VOLUME VENT VALVE FAIL OPEN)
MANUALLY SCRAM REACTOR 1
ACCEPTANCE CRITERIA: 1 1
RB FANS ISOLATE RB VENT. RAD INCREASE 1
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, ATTACHMENT 3 Q. INITIAL CONDITIONS:
RESET IC-19.
INPUT MALF. RD13A/B (SCRAM DISCH VOLUME LEAK) @l00% FOR 120 SECONDS.
MANUALLY SCRAM REACTOR ACCEPTANCE CRITERIA:
ARM'S INCREASE HI RANGE ARM INCREASE t
RB VENT RAD INCREASE RB FANS ISOLATE j R. INITIAL CONDITIONS:
RESET TO IC-19.
INPUT MALF. RD09A/B ( SCRAM DISCH VOLUME DRAIN VALVE FAIL OPEN)
ACCEPTANCE CRITERIA:
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RB SUMP AREA TEMP INCREASE ;
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