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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
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NI ..ID V ERMONT YAN KEE NUCLEAR POWER CORPORAT l'
V n
sCvCNTY ScVEN OROVC GTHCCT B.4.1.1 RuTi.Axo, WRF10NT 05701 REPLY TO; ENGINEERING OFFICE TURNPIKE ROAD WCSTDORO. M ass ACHUSETTS c15 81 T ELEP HCH E 617-366 90ll WVY 79-26 IIarch 1, 1979 United States Nuclear Regulatory Ccc=irsion Office of Inspection and Enforccnent Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 Attention: Mr. Boyce H. Grier, Director Refcrence: License No. DPR-23 (Docket No. 50-271)
Dear Sir:
Subject:
Vertont Yankee 1978 Annual Report (2) copics of the Vercent Yankee Enclosed herewith please find tvo Annual Report, which describes the facility changes, tests, This and experitents report conducted without prior NRC approval during the year 1978.
is submitted in accordance with 10 CFR 50.59(b) .
Uc trust this information is acceptable to you; however, should you have any questions, please contact us.
Very truly yours, VE?JiONT YANKEE NUCLEAR POWER CORPCEATION W W -
Robert H..Groce Licensing Engineer RIIG/cm .
Enclosurc 790314O G f
I. Operations Summary A. Changes in Facility Design
- 1. The following changes requiring authorization from the Commission were made:
a) EDCR 74-26, Revision 1, Poison Spent Fuel Racks EDCR 74-26, Revision 1 received commission approval on September 15, 1977. It was submitted for PORC review on 1/26/78 and was completed on 4/20/78. t This EDCR covers the change in spent fuel storage capacity at Vermont Yankee from the existing 600 spent fuel assemblies to 2000 assemblies. Presently, Phasc I of the design change has been completed, and will accommodate 1230 spent fuel assemblics. This change was accomplished by using "Boral," neutron-absorbing storage equipment designed specifically for Vermont Yankee by Programmed and Remote System (par).
The spent fuel storage modules (racks) are fabricated from the following:
- 1) Castings Upper and lower grid structures cast from 356-T51 aluminum and final machined to meet dimensional re-quirements form the basic cavity locations, and support the cavity cans which hold the Boral poison curtain parts. The lower casting supports all the static and dynamic loads from the rest of the rack structure and stored fuel.
- 2) Side Plates Four (4) one-half inch thick, 6061-T651 aluminum-side plates bolt to the upper and lower castings forming the sides of the rack. These side plates maintain the proper dimensional relationship between the two castings and transfer all structural loads between the two.
- 3) Cavity cans A strip of neutron-abscrbing poison curtain material (Boral is positioned midway between each adjacent pair of spent fuel assemblies. This strip of Boral extends vertically one inch above and below the
active fuel in the spent fuel asscablies and is held in position by cavity can assemblies whose upper and lower ends are captured in pockets in the grid castings. These cavity cans are fabricated from two concentric square 5052-H32 aluminum tubes. The Boral is assembled in the void between the walls of the two aluminum tuber.
The ends of the outer tube are formed over, above and below the Boral, and welded to the inner tube, scaling the Boral in place between the walls of the cavity cans. These cans are placed in alternate cavity locations so that a given cavity storage location will be surrounded by either the four walls of a single cavity can or the individual walls of the four adjacent cavity cans.
- 4) Rack Feet Each rack rests on the spent fuel pool floor on five adjustable feet. The vertical adjustment is provided to enabic plumb and level installation and thus close proximity of adjacent racks in the presence of uneven-ness of the pool liner. These feet are 304 stainless steel at the liner interface insulated from the alumi-num machined parts uhich mate with the lower rack casting. This construction precluded concern over galvanic corrosion induced by a dissimilar metal couple at an aluminum / stainless steel interface.
These parts are all anodized prior to assembly to minimize corrosion. Assembly is accomplished, in special jigs to maintain tolerances, by bolting the side plates to the upper and lower castings and threading the feet into the lower castings.
Seismic design for this storage equipment is predicated on each individual rack being free-standing in the pool.
Analyses show they would slide and/or rock slightly under the most extreme seismic conditions postulated for this plant. No damage would be incurred by this action, and the clearances shown on the installation drawing will accommodate the sliding motion with acceptable margins.
PORC concludec that EDCR 74-26, Revision 1, does not pose any unreviewed safety question; it'does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident.
- 2. The following changes not requiring Commission approval were made:
a) EDCR 73-20, Supplement 6 - Reactor Building Crane EDCR 73-20, Supplement 6, was completed on 9/1/78.
This supplement provided the remaining documents requiring to complete EDCR 73-20; the FSAR page changes and the final drawing list. These docu-ments were not available in their completed forn until final NRC acceptance was received and all re-quired additional modifications completed. That acceptance was obtained and no further modifications are required.
PORC concluded that EDCR 73-20, Supplement 6, does not pose any unreviewed safety question; it does not increase the probability of occurrence or consequence of an accident previously analyzed, and it does not create the possibility of a different type of accident.
b) EDCR 77 V10-25 A&B Valve Motor Operator Modification EDCR 77-9 was completed on 7/14/78. This change provided for modification of the existing type SMB-3-100 Limitorque The operator to type SB-3-100 operators on V10-25 A&B.
modification added a belleville spring inertia pack to the Limitorque operator. This spring pack becomes part of the operator drive sleeve assembly and allows the stem This nut freedom of movement in one or both directions.
feature provided for the absorption of valve seating forces by compression of the springs rather than by tightening of the wedge in the seat; in effect, reducing thus reducing the the rigidity of the valve structure, buildup of the valve seat forces during the period follow-ing torque or limit switch opening.
PORC concluded that EDCR 77-9 does not pose any unreviewed safety questions; it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident.
c) EDCR 77 UPS Design blodification EDCR 77-19 was completed 9/22/78. This design change removed certain extraneous components and circuits from the UPS to alleviate established operating re-straints and impreve system reliability.
4
- 1) The following trip fuactions were changed to alarm functions:
- a. AC Overvoltage
- b. AC Undervoltage (Fast)
- c. Logic Failure
- d. Leg Fuse Failure
- e. DC Overvoltage
- f. Leg Overtemperatures
- 2) Change the eutput circuit breaker to manual operation.
- 3) Remove output fuses.
- 4) Disable all power level and sync. circuits.
- 5) Disable photon coupler circuit.
- 6) Provide test points for DC volts, DC amps, and AC volts on front control panel.
- 7) Provide redundant logic power supply arrangement.
PORC concluded that EDCR 77-19 does not pose any unreviewed safety questions; it does not increase the probability of occurrence or consequence of an accident previously analyzed, and it does not create the possibility of a different type of accident.
d) EDCR 77-22, Revision 1 - Vermont Yankee Torus Modification Work on EDCR 77-22, Revision 1, was completed in 7/78.
This design change adds two reinforcement pinto assemblies and two plain plates to each of the 32 columns. This modification is part of the Torus Support long-tern program, which assures the torus will withstand new loads discovered since the plant was constructed.
The plant is now operating under the short-term pro-gram criteria which is a . factor of safety of 2 on the torus-to-column welds. By the end of the long-tern program, these welds must meet ASME Section III, Sub-section NE requirements, which is a factor of safety greater than 4. This, plus new load combinations, make it necessary to increase the weld capacity by approximately 2h.
Although the final loads are not known, they have been bounded to where a torus-to-column weld design can be established with reasonable assurance that additional work will not need to be done when the Long-Term Program Final Load Definition Report is issued.
This work will be completed prior to the end of the LTP because all analytical efforts to keep the factor of .
safety greater than 2 have been exhausted. The NRC knows the strength of the welds and expects the fix to be made rather than waiting for the end of the Long- i Term Program lks to 2 years from now. t i
Work on EDCR 77-22 was terminated when cracks developed in the torus during gusset installation and a new con-tractor was chosen to repair the torus. This repair was performed under EDCR 78-17. A new EDCR will be ,
written in 1979 to cover a revised gusset installation procedure.
PORC concluded that EDCR 77-22, Revision 1, does not pose any unreviewed safety question; it does not increase the ;
probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility f of a different type of accident.
e) EDCR 78 Permanent Fast Transfer Circuitry EDCR 78-03 was completed 10/2/78. This design change provided:
e
- 1. The addition of an "early b" contact on the normal source breaker to initiate bus transfer. The "carly b" contact closes when the breaker starts to open; use of the "early b" contact to initiate the trans-fer assures that the normal source breakers will successfully trip before the transfer is completed.
- 2. The addition of a high-speed synchrocheck relay to supervise both high-speed transfers and manual trans-fers. Use of this relay will ensure that the transfer is blocked whenever there is an out-of-phase situation.
- 3. The addition of residual voltage relays to permit out-of-phase residual voltage bus transfer, but only after the voltage has decayed to a safe value.
PORC concluded that EDCR 78-03 does not pose any unreviewed safety question; it does not increase the probabilit3 ef occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident.
. 1 f) EDCR 78 Torus Repair EDCR 78-17 was completed 8/9/78. This design change repaired areas of the torus shell damaged during the implementation of EDCR 77-22. The torus shell was ground to remove all cracks as well as the heat-affected zones of the butter / temper pads. Cround areas were well repaired as necessary to provide a minimum torus wall thickness of no less than 0.48 inches. This leaves all torus areas with a factor of safety equal to or better than that accepted by the NRC as part of the Torus Short-Term Program.
PORC concluded that EDCR 78-17 does not pose any unreviewed safety question; it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident.
g) EDCR 78-17, Revision 1 EDCR 78-17, Revision 1, was completed 8/9/78. This change to EDCR 78-17 resolves comments generated during the review of the design change. The comments were administrative in nature and were required to be satisfied prior to closecut of the Job Order File.
PORC concluded that EDCR 78-17, Revision 1, does not posc any unreviewed safety question; it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident.
h) EDCR 78 RPS MG Set Modification EDCR 78-19 was completed 10/7/78. This design change replaced the existing over/under voltage protection for each MG set with a new solid state over/under voltage sensor and a new time-delay relay. The new over/under voltage device and the existing under-frequence relay was used with the time-delay relay to trip the MG set output circuit breaker after a time delay of approxi mately five seconds. The five-second time delay pre-vents unnecessary tripping due to transient conditions.
PORC concluded that EDCR 78-19 does not pose any unreviewed safety questions; it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident.
- 1) PDCR 77 LPCI Injection Valves V1025 A&B Redundant Automatic Openine Logic PDCR 77-4 was completed 7/14/78. This design change provided the installation of redundant contacts in the auto open logic for the inboard LPCI Injection Valve V10-25 A&B. This change ensures that both V10-25 A&B receives an automatic "open" signal in the event of a LOCA assuming a single failure of either logic train.
The existing relays that provide the redundant auto-matic open signal for the outboard LPCI Injection Valves V10-27 A&B have the necessary spare contacts to f acilitate this change. The relays selected for use, and the asso-ciated wiring comply with the technical description pro-vided in Proposed Change No. 21.
PORC concluded that PDCR 77-4 does not pose any unreviewed safety questions; it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident.
j) PDCR 77 RCIC Turbine Hydraulic Priming PDCR 77-6 was completed 7/19/78. This change provided the installation of an auxiliary oil sump in the oil supply line to the Woodward EG-R Hydraulic Actuator to climinate the possibility of starving the oil supply to the actuator during quick-start transients which can result in a turbine overspeed trip.
PORC concluded that PDCR 77-6 does not pose any unreviewed safety questions; it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident, k) PDCR 77 Supplement 1 - RCIC Turbine Hydraulic Priming PDCR 77-6, Supplement 1, was completed 7/19/78. This supplement to PDCR 77-6 is submitted to incorporate additional modifications to the HPCI and RCIC Hydraulic Piping that will allow addition of the auxiliary oil sump as described in the original PDCR.
PORC concluded that PDCR 77-6, Supplement 1, does not pose any unreviewed safety questions; it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident.
i J
- 1) PDCR 77 Create a New Construction Joint on the Reactor Building East Wall PDCR 77-7 was completed 9/18/78. This change provided a new construction joint on the Reactor Building east wall. This was accomplished by saw cutting a one-inch by one-inch joint on the exterior f ace of the wall from 252'-6" elevation to the top of the concrete wall. The joint was then filled with a flexible backing and an clastomeric sealant on the outside.
PORC concluded that PDCR 77-7 oues not pose any unreviewed safety questions; it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident.
m) PDCR 77 Elinination of RWCU Flow Switch PDCR 77-9 was completed 7/28/78. This change provided for removal of flow switches and their replacement with a spool piece. PMR 77-20 addressed the electrical por-tion of the switches.
PORC concluded that PDCR 77-9 does not pose any unreviewed safety questions; it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident.
n) PDCR 78 Reactor Building Header & Standnine System t
PDCR 78-04 was completed 10/4/78. This change added a fire header and standpipe in the Reactor Building.
A supply header is provided in the torus area, fed by two independent sources of supply from the inner turbine fire loop. A new standpipe (with hose racks at each elevation above grade) is provided in the southeast area of the building. The existing stand-pipe in the northwest area of the building will be enlarged and fed by the new header. This will pro-vide adequate coverage of the Reactor Building with 75 feet of hose at each rack.
The header and standpipe system also provides a source .
of supply to the MG set foam syster at elevation 280',
and the cable penetration area sprinkler system at eleva-tion 232'.
PORC concluded that PDCR 78-10 does not pose any unreviewed safety questions; it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident, t) PDCR 78 Turbine Buildinn Loading Bay Sprinkler Systen PDCR 78-11 was completed 10/6/78. This design change provided an automatic sprinkler systen to protect the laydown area (loading bay) in the Turbine Building from a notor vehicle fire. This systen is intended to mini-nize the potential for large uncontrolled fires which could threaten the integrity of the Turbine Euilding.
PORC concluded that PDCR 78-11 does not pose any unreviewed safety questions; it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident, u) PAR 77 Addition of Fourth Service and Instrument Air Compressor PAR 77-9 was completed 4/20/78. This PAR provided for the addition of a fourth Service and Instrucent Air Compressor, changing of the cooling water piping to copper, and codificatica of the electrical controls.
PORC concluded that PAR 77-9 does not pose any unreviewed safety questions; it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident.
v) PMR 77 AEOG Test Switches _
PMR 77-19 was completed 7/14/78. This PMR provided for the addition of keylock test switches to isolate the selected channel AEOG trip logic during naintenance.
This change simplifies naintenance by avoiding lifting leads and placing jumpers to isolate the entire AEOG trip logic.
PORC concluded that PMR 77-19 does not pose any unreviewed safety questions; it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident.
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PORC concluded that PDCR 78-05 does not pose any unreviewed I safety questions; it does not increase the probability of l occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident.
p) PDCR 78 Recire. MC Set Foam Suppression System PDCR 78-7 was completed 10/11/78. This design change provided an automatic foam suppression system for the Recirc. - MG sets. This system provides exposure pro-tection for adjace.it reactor vessel instrumentation racks and safety-class cable trays.
PORC concluded that PDCR 78-7 does not pose any unreviewed safety questions; it does not increase the probability of ;
occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident.
q) PDCR 78 Diesel Fire Pump Sprinkler System PDCR 78-8 was completed 9/25/78. This design change provided an automatic sprinkler system over the diesel fire pump area to provide exposure protection for the adjacent electric fire pump and service water pumps.
PORC concluded that PDCR 78-8 does not pose any unreviewed safety questions; it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident.
i r) PDCR 78 Diesel Generator Rooms A & B Manual Sprinkler Systen PDCR 78-9 was completed 9/19/78. This design change ,
provided manually operated sprinkler systems for each diesel generator room in order to prevent a fire in l one diesel generator room from affecting the operability of the other diesel generator.
8 PORC concluded that PDCR 78-9 does not pose any unreviewed safety questions; it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident, s) PDCR 78 Reactor Building Cable Penetration Area Sprinkler Svst_em PDCR 78-10 was completed 10/6/78. This design change provided an area preaction sprinkler system at the northwest corner of the Reactor Building to provided protection for redundant safety-related cables pene-trating the Reactor Building / Cable Vault walls.
w) PAR 77 Low Flow Trip for Reactor Water Cleanup Pumas PAR 77-20 was cenpleted 7/22/78. This PAR changed the instrunentation used in determining the low-flow con-dition. Sensor and indicating portions already exist, an alarn unit was installed to provide relay contacts in a logic sequence to an aux 1]iary relay. Annunciator nomenclature was changed to indicate a pump trip rather than a low flow. Annunciator indication was also changed because present circuitry actually indicates a pump trip for reasons in addition to low flow.
PORC concluded that PAR 77-20 does not pose any unreviewed safety questions; it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident.
x) PAR 77 Fire Protection Loop Isolation Valves PAR 77-23 was completed 9/24/78. This PAR provided additional isolation valves for the inside fire loop to allow for operational flexibility in the event of the loss of vital and non-vital hose stations.
PORC concluded that PAR 77-23 does not pose any unreviewed safety questions, it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident, y) PAR 77 Renoval of Acid Inlet Solenoid Valve on Makeun Denin, Systen PAR 77-26 was completed 4/5/78. The solenoid valve on the Makeup Demin. acid inlet line continually fails due to the acid environment to which it is exposed. This situation makes it necessary to override the valve, keeping it open, while isolating flow through the use of a nanual valve. Since the solenoid valve, when working properly, must be manually opened from the local control panel, removal of this valve does not create an operational probler.
PORC concluded that PAR 77-26 does not pose any unreviewed safety questions; it does not increase the prcbability of occurrence er consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident,
z) PAR 78 Reroute Domineralized 'Jater to Radwaste_
Monitor for Flushing PAR 78-4 was ccmpleted 5/31/78. This alteration changed the flushing supply for the Radwaste Discharge Monitor fron condensate water to demineralized water.
By using demineralized water as the flushing agent, the potential for an unmonitored release is decreased.
PORC concluded that PAR 78-4 does not pose any unreviewed safety questions; it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident.
sa) PAR 78 Stack Gas Lightning Protection PAR 78-7 was completed 10/13/78. This alteration re-duced lightning effects in the stack gas monitor cable by the installation of a new coaxial cable inside a continuous length of grounded steel conduit. Lightning protection is thereby achieved while maintaining noise immunity.
PORC concluded that PAR 78-7 does not pose any unreviewed safety questions; it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident.
bb) PAR 78 Stack Gas Isolation System Mechanical, Modification PAR 78-9 was completed 7/22/78. This alteration re-placed the solenoid valves on the stack filter drain line (SEI-107-2 A&B) with normally closed manual valves to provide necessary isolation conditions regardless of the electrical status of the stack valve dolenoid coils.
PORC concluded that PAR 78-9 does not pose any unreviewed safety questions; it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident.
cc) PA_R 78 Stack Gas Isolation Svstem Electrical Modification PAR 78-11 was completed 7/13/78. This alteration pro-vides for the removal of the SEI-107-2 ASB valves control cables frem the Stack Isolation Valve FCV-ll control circuitry (see PAR 78-09 above). This PAR prevents electrical failure of the solenoids from affecting the operability of FCV-11.
h .
PORC concluded that PAR 78-11 does not pose any unreviewed safety questions; it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accidcut.
dd) PAR 78 Removal of Press / Temp Instrumentation on Old A0G Line PAR 78-13 was completed 9/21/78. This alteration re-moves instrumentation and solenoids from an unused section of Off-Gas piping. By removing this instru-mentation, a source of spurious trips for the 516 A/B valves are eliminated as well as a possibic source of ignition for any hydrogen which may collect in this pipeline.
PORC concluded that PAR 78-13 does not pose any unreviewed safety questions; it does not increase the probability of occurrence or consequences of an accident previosuly analyzed, and it does not create the possibility of a different type of accident.
ee) PAR 78 Addition of Keylock Switch to RMCS for Service Platform Interlock PAR 78-15 uas completed 8/4/78. This alteration pro-vided Control Room supervision of the refuel interlock associated with the service platform. In the past, a
" bypass plug" was installed in conjunction with the service platform power cabic prior to operating the platform. This new keylock switch eliminates the ne-cessity of the bypass plug without removing any pro-tection provided by that plug.
PORC concluded that PAR 78-15 does not pose any unrevieved safety questions; it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident.
ff) PAR 78 Mod. of Turbine Steam Flow / Shutdown Level Recorder PAR 78-17 was completed 8/8/78. This alteration can provide continuous wide-range level indication in the Control Room whenever the reactor recirc pumps are at minimum speed by using existing instrumentation, speci-fically Recorder G-98 in CRP 9-5.
PORC concluded that PAR 78-17 does not pose any unreviewed safety questions; it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident.
gg) PAR 78 Diesel Fire Pump 011 Sample Connection PAR 78-19 was completed 4/18/78. This change adds a sample line and valve to the Diesel Fire Pump fuel line which will allow oil samples to be taken as re-quired Tech. Spec. Section 4.13.B.2.b.
PORC concluded that PAR 78-19 does not oose any unreviewed safety questions; it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident. I hh) PAR 78 Condensate Demin. Flow Balancinn Svstem >
Additions PAR 78-20 was completed 10/3/78. This alteration pro-vided an override system by inserting a flow balancing network on the master control output of the condensate demineralizer vessel during a high AP condition. This addition provides further protection against a loss of }
I flow downstrean of the Condensate Demineralizer System.
PORC concluded that PAR 78-20 does not pose any unreviewed :
I safety questions; it does not increase the probability of eccurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident.
ii) PAR 78 Air Compressor Flushing Connections PAR 78-35 was completed 11/27/78. This alteration pro-vided the ability to flush service water f r.a the air compressor cooling lines to prevent untreated service water from entering the TBCCW system in the event alter-nate cooling is required.
PORC concluded that PAR 78-35 does not pose any unreviewed safety questions; it does not increase the probability of occurrence or consequences of an accident previously analyzed, and it does not create the possibility of a different type of accident.