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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K3161999-10-19019 October 1999 Forwards Amend 195 to License DPR-61 & Safety Evaluation. Amend Deletes Certain TSs Either No Longer Applicable to Permanently Shutdown & Defueled State of Reactor or Duplicate Regulatory Requirements CY-99-137, Notifies NRC of Intent to Apply Haddam Neck Plant 10CFR50 App B,Qa Program to Activities Related to Development of ISFSI at Haddam1999-10-12012 October 1999 Notifies NRC of Intent to Apply Haddam Neck Plant 10CFR50 App B,Qa Program to Activities Related to Development of ISFSI at Haddam DD-99-11, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-11) Expired & That Commission Declined Any Review.Decision Became Final Action on 9910041999-10-0808 October 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-11) Expired & That Commission Declined Any Review.Decision Became Final Action on 991004 ML20212L1261999-10-0404 October 1999 Forwards Viewgraphs Presented by Licensee at 990923 Meeting with Nrc,In Response to Request ML20212D0341999-09-20020 September 1999 Expresses Appreciation for Accepting NRC Request for Tour of Haddam Neck Facility During on 991014.Invites R Mellor to Participate in NRC 1999 Decommissioninng Power Reactor Work- Shop:Nrc Insp Program at Decommissioning Power Reactors CY-99-111, Submits Clarification of Changes Made to Connecticut Yankee QA Program,Per Util 990810 Submittal.Change Will Be Submitted to NRC in Dec 1999 as Part of Annual Update1999-09-0202 September 1999 Submits Clarification of Changes Made to Connecticut Yankee QA Program,Per Util 990810 Submittal.Change Will Be Submitted to NRC in Dec 1999 as Part of Annual Update ML20211E8051999-08-20020 August 1999 Forwards Insp Rept 50-213/99-02 on 990420-0719.No Violations Noted.Completion of Corrective Actions for Spent Fuel Bldg Ventilation Issues Adequate ML20210J6021999-08-0202 August 1999 Informs That Info Re Orise Technical Survey Assistance to NRC at CT Yankee Is to Include Copies of Listed Documents CY-99-048, Forwards Cyap Rept CY-HP-0031,Rev 0, Bounding Dose Assessment for Offsite Radioactive Matls1999-07-29029 July 1999 Forwards Cyap Rept CY-HP-0031,Rev 0, Bounding Dose Assessment for Offsite Radioactive Matls CY-99-066, Forwards Revised Plan for Recovery of Licensed Matl from Offsite Locations.Completion of Implementation of Plan During Summer of 1999 Is Planned,Contingent on Support Extended by Property Owners,Weather & Uncontrolled Factors1999-07-20020 July 1999 Forwards Revised Plan for Recovery of Licensed Matl from Offsite Locations.Completion of Implementation of Plan During Summer of 1999 Is Planned,Contingent on Support Extended by Property Owners,Weather & Uncontrolled Factors ML20210C1491999-07-0101 July 1999 Responds to ,Which Responded to NRC Ltr & NOV & Informs That Engagement in Any Similar Wrongdoing in Future May Result in More Significant Enforcement Action. No Further Action Will Be Taken at This Time ML20209C3911999-06-30030 June 1999 Forwards TS Page 6-3 for Haddam Neck Plant 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 ML20195F9011999-06-0909 June 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp 50-213/98-06 on 990226. Util Did Not Agree with Disposition of Issue Cited as Severity Level IV Violation.Violation Will Be Noncited ML20195H3591999-06-0202 June 1999 Responds to NRC Re Violations Noted in Insp of License DPR-61.Corrective Actions:Disciplinary Actions Were Taken by Util Against Jm Foley & Individual & Departmental Emphasis Is Placed on New HP Stds & Expectations ML20207E9031999-06-0202 June 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Mt Masnik Will Be Section Chief for Haddam Neck.Organization Chart Encl ML20207B9301999-05-25025 May 1999 Responds to 990114 Correspondence Re Changes to Plant Defueled Physical Security Plan Rev 1 Submitted Under 10CFR50.54(p).Implementation of Changes Subj to Insp to Confirm Changes Have Not Decreased Security Plan ML20207G1761999-05-21021 May 1999 Forwards Insp Rept 50-213/99-01 on 980119-990419 & Closure of CAL 1-97-010.No Violations Noted.Conduct of Activities Associated with Control of Radiological Work at Haddam Neck Generally Characterized as Careful & Thorough ML20206R7221999-05-12012 May 1999 Refers to Investigation 1-97-031 on 970616-0718 & Forwards Nov.Investigation Found That Recipient Deliberately Did Not Follow Radiation Protection Procedures,Falsified Documents & Provided Incomplete & Inaccurate Info to NRC ML20206R7021999-05-12012 May 1999 Refers to Investigation 1-97-008 Conducted by Region I & Forwards Notice of Violation.Investigation Found That Recipient Deliberately Attempted to Conceal Release of Contaminated Video Equipment ML20206R8051999-05-12012 May 1999 Responds to 3 Investigations,Repts 1-97-031,008 & 1-98-008 Between 970314 & 980722 as Well as Insp Conducted Between 980720 & 1102.Forwards Synopsis of 3rd OI Investigation 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 CY-99-057, Forwards 1998 Annual Radioactive Effluent Rept for HNP, & Rev 10 to Remodcm. with Summary of Quantities of Solid Radwaste & Liquid & Gaseous Effluents,As Well as Summary of Assessment of Max Individual Dose1999-04-30030 April 1999 Forwards 1998 Annual Radioactive Effluent Rept for HNP, & Rev 10 to Remodcm. with Summary of Quantities of Solid Radwaste & Liquid & Gaseous Effluents,As Well as Summary of Assessment of Max Individual Dose ML20206C8631999-04-28028 April 1999 Forwards Amend 194 to License DPR-61 & Safety Evaluation. Amend Authorizes Relocation of Requirements Related to Seismic Monitoring Instrumentation from TSs to Technical Requirements Manual ML20206A6871999-04-22022 April 1999 Informs of Completion of Review of Re Nepco in Capacity as Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee Atomic Power Co ML20210V5221999-04-0808 April 1999 Discusses Continued Performance of Technical Assistance Activities for NRC & Environ Survey & Site Assessment Program (Essap) Survey Assistance at Cy IR 05000213/19960121999-04-0505 April 1999 Discusses NRC Insp Repts 50-213/96-12 & 50-213/98-04 on 961102-27 Re Airborne Radioactivity Contamination Event That Occurred in Fuel Transfer Canal & Reactor Cavity in Nov 1996.Notice of Violation Encl ML20205J7931999-04-0505 April 1999 Discusses NRC Insp Repts 50-213/96-12 & 50-213/98-04 on 961102-27 Re Airborne Radioactivity Contamination Event That Occurred in Fuel Transfer Canal & Reactor Cavity in Nov 1996.Notice of Violation Encl CY-99-042, Provides Info on Status of Decommissioning Funding for Haddam Neck Plant1999-03-31031 March 1999 Provides Info on Status of Decommissioning Funding for Haddam Neck Plant 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 CY-99-024, Responds to Violations Noted in Insp Rept 50-213/98-06. Corrective Actions:Meetings Were Held with Contractor Mgt, Disciplinary Action Against Worker Was Taken & Notices Alerting Workers to HRA Controls Were Posted1999-03-29029 March 1999 Responds to Violations Noted in Insp Rept 50-213/98-06. Corrective Actions:Meetings Were Held with Contractor Mgt, Disciplinary Action Against Worker Was Taken & Notices Alerting Workers to HRA Controls Were Posted B17697, Notifies NRC of Amount of Property Insurance Coverage, Effective 990401,for HNP & Mnps,Units 1,2 & 3,per Provisions of 10CFR50.54(w)1999-03-12012 March 1999 Notifies NRC of Amount of Property Insurance Coverage, Effective 990401,for HNP & Mnps,Units 1,2 & 3,per Provisions of 10CFR50.54(w) CY-99-032, Clarifies Info Re TRM Change Submitted with Re Proposed Rev to TSs on Seismic Monitoring1999-03-0909 March 1999 Clarifies Info Re TRM Change Submitted with Re Proposed Rev to TSs on Seismic Monitoring ML20207B6641999-02-26026 February 1999 Forwards Insp Rept 50-213/98-06 on 981103-990118 & Notice of Violation Re Locked High Radiation Area Doors That Were Found Unlocked by Staff.Security Program Was Also Inspected ML20204C6901999-02-22022 February 1999 Informs That Public Citizen Waives Copyright for 5th Edition of Nuclear Lemon So NRC May Reproduce for Purpose of Contributing to NRC Recommended Improvements to Oversight Process for Nuclear Power Reactors ML20203H9621999-02-17017 February 1999 Responds to to Dk Rathbun Which Forwarded Number of Questions from Constituent Re Spent Fuel Decommissioned Nuclear plants.NUREG-1628, Staff Responses to Frequently Asked Questions Re Decommissioning of NPPs Encl.W/O Encl CY-99-005, Responds to NRC 981221 RAI Re Amend 193 to License to Reflect Permanent Shutdown Condition of Plant.Licensee Withdrawing 981030 (CY-98-199) Request & Will Submit Corrections in Future Proposed Rev to TS1999-01-29029 January 1999 Responds to NRC 981221 RAI Re Amend 193 to License to Reflect Permanent Shutdown Condition of Plant.Licensee Withdrawing 981030 (CY-98-199) Request & Will Submit Corrections in Future Proposed Rev to TS CY-99-023, Provides Summary of Understandings Reached During 990108 Meeting Between Util & CT Dept of Environ Protection Re Dike Area Rainwater Reporting Protocol1999-01-28028 January 1999 Provides Summary of Understandings Reached During 990108 Meeting Between Util & CT Dept of Environ Protection Re Dike Area Rainwater Reporting Protocol ML20203H9711999-01-21021 January 1999 Requests Response to Concerns Raised by Constitutent M Marucci Re Spent Fuel at Decommissioned Nuclear Plants CY-99-002, Forwards Response to NRC 981203 RAI Re Proposed License Amend to Relocate Requirements for Seismic Monitoring Instrumentation from Section 3/4.3.3.3 of TS to Trm. Supporting TSs Encl1999-01-18018 January 1999 Forwards Response to NRC 981203 RAI Re Proposed License Amend to Relocate Requirements for Seismic Monitoring Instrumentation from Section 3/4.3.3.3 of TS to Trm. Supporting TSs Encl CY-99-010, Provides Special Rept Concerning Potential of Radiation Exposure Due to Hypothetical Explosive Attack to Facility. Without Encl1999-01-14014 January 1999 Provides Special Rept Concerning Potential of Radiation Exposure Due to Hypothetical Explosive Attack to Facility. Without Encl CY-99-009, Forwards Rev 1 to Haddam Neck Plant Defueled Physical Security Plan,Per 10CFR50.54(p).Rev Does Not Decrease Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 & 2.7901999-01-14014 January 1999 Forwards Rev 1 to Haddam Neck Plant Defueled Physical Security Plan,Per 10CFR50.54(p).Rev Does Not Decrease Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 & 2.790 ML20206R6051999-01-11011 January 1999 Ack Receipt of Submiting Sf Mgt Plan.Staff Has Reviewed Plan & Notes Plan to Store Sf in SFP Until DOE Takes Physical Possession of Fuel DD-98-12, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision DD-98-12 Has Expired.Decision Became Final Agency Action on 981211. with Certificate of Svc.Served on 9812221998-12-22022 December 1998 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision DD-98-12 Has Expired.Decision Became Final Agency Action on 981211. with Certificate of Svc.Served on 981222 CY-98-142, Forwards Proposed Rev 2 of Cyap QAP for Info & Approval of Exception Number 8 of App E of Cy Qap.Copy of Rev 2 Showing Changes from Rev 1 Also Included1998-12-22022 December 1998 Forwards Proposed Rev 2 of Cyap QAP for Info & Approval of Exception Number 8 of App E of Cy Qap.Copy of Rev 2 Showing Changes from Rev 1 Also Included ML20198R1321998-12-21021 December 1998 Forwards Insp Rept 50-213/98-05 on 980720-1102.No Violations Noted.Insp Completes Review of Licensee Actions Described in ,In Response to NOV & Proposed Imposition of Civil Penalties ML20198K8651998-12-21021 December 1998 Ack Receipt of ,Requesting Corrected Pages to Be Issued for License Amend 193,issued on 980630.Informs That Inconsistencies Found When Comparing Corrected Pages Submitted on 981030 & License Amend Application CY-98-201, Provides Clarification of NRC Staff SE for Amend 193 Which Approved HNP Defueled TSs1998-12-0303 December 1998 Provides Clarification of NRC Staff SE for Amend 193 Which Approved HNP Defueled TSs IR 05000213/19980041998-11-27027 November 1998 Forwards Special Insp Rept 50-213/98-04 of Licensee Performance During Reactor Coolant Sys Chemical Decontamination ML20195J3571998-11-19019 November 1998 Forwards Exemption from Certain Requirements of 10CFR50.54(w) & 10CFR140.Exemption Submitted in Response to 971007 Application & Suppls & 1218,requesting Reduction in Amount of Insurance Required for Facility 1999-09-20
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARCY-99-137, Notifies NRC of Intent to Apply Haddam Neck Plant 10CFR50 App B,Qa Program to Activities Related to Development of ISFSI at Haddam1999-10-12012 October 1999 Notifies NRC of Intent to Apply Haddam Neck Plant 10CFR50 App B,Qa Program to Activities Related to Development of ISFSI at Haddam CY-99-111, Submits Clarification of Changes Made to Connecticut Yankee QA Program,Per Util 990810 Submittal.Change Will Be Submitted to NRC in Dec 1999 as Part of Annual Update1999-09-0202 September 1999 Submits Clarification of Changes Made to Connecticut Yankee QA Program,Per Util 990810 Submittal.Change Will Be Submitted to NRC in Dec 1999 as Part of Annual Update CY-99-048, Forwards Cyap Rept CY-HP-0031,Rev 0, Bounding Dose Assessment for Offsite Radioactive Matls1999-07-29029 July 1999 Forwards Cyap Rept CY-HP-0031,Rev 0, Bounding Dose Assessment for Offsite Radioactive Matls CY-99-066, Forwards Revised Plan for Recovery of Licensed Matl from Offsite Locations.Completion of Implementation of Plan During Summer of 1999 Is Planned,Contingent on Support Extended by Property Owners,Weather & Uncontrolled Factors1999-07-20020 July 1999 Forwards Revised Plan for Recovery of Licensed Matl from Offsite Locations.Completion of Implementation of Plan During Summer of 1999 Is Planned,Contingent on Support Extended by Property Owners,Weather & Uncontrolled Factors ML20209C3911999-06-30030 June 1999 Forwards TS Page 6-3 for Haddam Neck Plant 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 ML20195H3591999-06-0202 June 1999 Responds to NRC Re Violations Noted in Insp of License DPR-61.Corrective Actions:Disciplinary Actions Were Taken by Util Against Jm Foley & Individual & Departmental Emphasis Is Placed on New HP Stds & Expectations CY-99-057, Forwards 1998 Annual Radioactive Effluent Rept for HNP, & Rev 10 to Remodcm. with Summary of Quantities of Solid Radwaste & Liquid & Gaseous Effluents,As Well as Summary of Assessment of Max Individual Dose1999-04-30030 April 1999 Forwards 1998 Annual Radioactive Effluent Rept for HNP, & Rev 10 to Remodcm. with Summary of Quantities of Solid Radwaste & Liquid & Gaseous Effluents,As Well as Summary of Assessment of Max Individual Dose 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 ML20210V5221999-04-0808 April 1999 Discusses Continued Performance of Technical Assistance Activities for NRC & Environ Survey & Site Assessment Program (Essap) Survey Assistance at Cy CY-99-042, Provides Info on Status of Decommissioning Funding for Haddam Neck Plant1999-03-31031 March 1999 Provides Info on Status of Decommissioning Funding for Haddam Neck Plant 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 CY-99-024, Responds to Violations Noted in Insp Rept 50-213/98-06. Corrective Actions:Meetings Were Held with Contractor Mgt, Disciplinary Action Against Worker Was Taken & Notices Alerting Workers to HRA Controls Were Posted1999-03-29029 March 1999 Responds to Violations Noted in Insp Rept 50-213/98-06. Corrective Actions:Meetings Were Held with Contractor Mgt, Disciplinary Action Against Worker Was Taken & Notices Alerting Workers to HRA Controls Were Posted B17697, Notifies NRC of Amount of Property Insurance Coverage, Effective 990401,for HNP & Mnps,Units 1,2 & 3,per Provisions of 10CFR50.54(w)1999-03-12012 March 1999 Notifies NRC of Amount of Property Insurance Coverage, Effective 990401,for HNP & Mnps,Units 1,2 & 3,per Provisions of 10CFR50.54(w) CY-99-032, Clarifies Info Re TRM Change Submitted with Re Proposed Rev to TSs on Seismic Monitoring1999-03-0909 March 1999 Clarifies Info Re TRM Change Submitted with Re Proposed Rev to TSs on Seismic Monitoring ML20204C6901999-02-22022 February 1999 Informs That Public Citizen Waives Copyright for 5th Edition of Nuclear Lemon So NRC May Reproduce for Purpose of Contributing to NRC Recommended Improvements to Oversight Process for Nuclear Power Reactors CY-99-005, Responds to NRC 981221 RAI Re Amend 193 to License to Reflect Permanent Shutdown Condition of Plant.Licensee Withdrawing 981030 (CY-98-199) Request & Will Submit Corrections in Future Proposed Rev to TS1999-01-29029 January 1999 Responds to NRC 981221 RAI Re Amend 193 to License to Reflect Permanent Shutdown Condition of Plant.Licensee Withdrawing 981030 (CY-98-199) Request & Will Submit Corrections in Future Proposed Rev to TS ML20203H9711999-01-21021 January 1999 Requests Response to Concerns Raised by Constitutent M Marucci Re Spent Fuel at Decommissioned Nuclear Plants CY-99-002, Forwards Response to NRC 981203 RAI Re Proposed License Amend to Relocate Requirements for Seismic Monitoring Instrumentation from Section 3/4.3.3.3 of TS to Trm. Supporting TSs Encl1999-01-18018 January 1999 Forwards Response to NRC 981203 RAI Re Proposed License Amend to Relocate Requirements for Seismic Monitoring Instrumentation from Section 3/4.3.3.3 of TS to Trm. Supporting TSs Encl CY-99-009, Forwards Rev 1 to Haddam Neck Plant Defueled Physical Security Plan,Per 10CFR50.54(p).Rev Does Not Decrease Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 & 2.7901999-01-14014 January 1999 Forwards Rev 1 to Haddam Neck Plant Defueled Physical Security Plan,Per 10CFR50.54(p).Rev Does Not Decrease Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 & 2.790 CY-99-010, Provides Special Rept Concerning Potential of Radiation Exposure Due to Hypothetical Explosive Attack to Facility. Without Encl1999-01-14014 January 1999 Provides Special Rept Concerning Potential of Radiation Exposure Due to Hypothetical Explosive Attack to Facility. Without Encl CY-98-142, Forwards Proposed Rev 2 of Cyap QAP for Info & Approval of Exception Number 8 of App E of Cy Qap.Copy of Rev 2 Showing Changes from Rev 1 Also Included1998-12-22022 December 1998 Forwards Proposed Rev 2 of Cyap QAP for Info & Approval of Exception Number 8 of App E of Cy Qap.Copy of Rev 2 Showing Changes from Rev 1 Also Included CY-98-201, Provides Clarification of NRC Staff SE for Amend 193 Which Approved HNP Defueled TSs1998-12-0303 December 1998 Provides Clarification of NRC Staff SE for Amend 193 Which Approved HNP Defueled TSs CY-98-191, Provides Notification That Util Implemented Defueled Emergency Plan for HNP on 981001.Util Completed Annual Exercise Required by Subj Plan & 10CFR50.471998-11-0505 November 1998 Provides Notification That Util Implemented Defueled Emergency Plan for HNP on 981001.Util Completed Annual Exercise Required by Subj Plan & 10CFR50.47 CY-98-140, Provides Commitment to Maintain Water Chemistry Requirements in HNP Technical Requirements Manual1998-11-0202 November 1998 Provides Commitment to Maintain Water Chemistry Requirements in HNP Technical Requirements Manual CY-98-183, Forwards Revised License Amend 193 TS Pages to Correct Amend Number on Pages Not Changed by Amend 193.No Commitments Contained within Ltr1998-10-30030 October 1998 Forwards Revised License Amend 193 TS Pages to Correct Amend Number on Pages Not Changed by Amend 193.No Commitments Contained within Ltr CY-98-199, Forwards Listing of Corrections Made & Revised Pages for Proposed License Amend 193.Ltr Also Transmits Repaginated Pages for TS Index & Section 1,per Request of NRC Project Manager1998-10-30030 October 1998 Forwards Listing of Corrections Made & Revised Pages for Proposed License Amend 193.Ltr Also Transmits Repaginated Pages for TS Index & Section 1,per Request of NRC Project Manager CY-98-062, Updates Info of Historical Nature in Response to Both NRC Historical Review Rept & NRC Insp Rept 50-213/97-11 Open Items1998-10-28028 October 1998 Updates Info of Historical Nature in Response to Both NRC Historical Review Rept & NRC Insp Rept 50-213/97-11 Open Items CY-98-154, Forwards Sf Mgt Plan for Haddam Neck Plant.Plan Submits Info on Mgt & Funding for Program to Safely Store Sf Following Permanent Cessation of Power Operations Until Title Is Transferred to DOE1998-10-28028 October 1998 Forwards Sf Mgt Plan for Haddam Neck Plant.Plan Submits Info on Mgt & Funding for Program to Safely Store Sf Following Permanent Cessation of Power Operations Until Title Is Transferred to DOE CY-98-129, Provides Supplemental Info to 980629 Response to 2.206 Petition Questions on Spent Fuel Cooling Methods.Util Pending Commitment Made within Ltr Stated1998-10-14014 October 1998 Provides Supplemental Info to 980629 Response to 2.206 Petition Questions on Spent Fuel Cooling Methods.Util Pending Commitment Made within Ltr Stated CY-98-186, Provides Notification of Organizational Changes Which Affect Cyap.Organization Chart,Biographical Profile of K Heider & Revised Distribution List for NRC Correspondence,Encl1998-10-0202 October 1998 Provides Notification of Organizational Changes Which Affect Cyap.Organization Chart,Biographical Profile of K Heider & Revised Distribution List for NRC Correspondence,Encl CY-98-153, Forwards Final Response to NRC 961009 RAI Re Configuration Mgt Project at Plant.No New Commitments Made within Ltr or Attachment1998-09-30030 September 1998 Forwards Final Response to NRC 961009 RAI Re Configuration Mgt Project at Plant.No New Commitments Made within Ltr or Attachment CY-98-157, Responds to NRC Request That Cyap Submit Proposed License Amend to Include Fuel Storage Pool Water Chemistry Program within Haddam Neck Plant Ts.Cyap Considers That Amend Is Not Necessary for Listed Reasons.Procedure Encl1998-09-28028 September 1998 Responds to NRC Request That Cyap Submit Proposed License Amend to Include Fuel Storage Pool Water Chemistry Program within Haddam Neck Plant Ts.Cyap Considers That Amend Is Not Necessary for Listed Reasons.Procedure Encl B17440, Corrects Errors in Ltrs & 980225 Re semi-annual Fitness for Duty Performance Data for Jan-June 1998 & July-Dec 19971998-09-24024 September 1998 Corrects Errors in Ltrs & 980225 Re semi-annual Fitness for Duty Performance Data for Jan-June 1998 & July-Dec 1997 CY-98-151, Responds to NRC Re Violations Noted in Insp Rept 50-213/98-03.Corrective Actions:Root Cause Team Has Determined That Shift Managers Initial Reportability Decision Was Not Correct1998-09-21021 September 1998 Responds to NRC Re Violations Noted in Insp Rept 50-213/98-03.Corrective Actions:Root Cause Team Has Determined That Shift Managers Initial Reportability Decision Was Not Correct ML20153G3891998-09-14014 September 1998 Informs That Union of Concerned Scientists Fully Supports Citizens Awareness Network Petition Filed Pursuant to 10CFR2.206,seeking to Revoke or Suspend License for Haddam Neck Nuclear Plant ML20154J9861998-09-11011 September 1998 Forwards for Service Upon Lj Callan,Jc Hoyle & Commission, Request for NRC to Revoke Connecticut Yankee Atomic Power Co License to Operate Haddam Neck Reactor Pursuant to 10CFR2.206 ML20154J9991998-09-11011 September 1998 Requests NRC Take Immediate Action to Revoke Util License to Operate Haddam Neck Nuclear Power Station Pursuant to 10CFR2.206 B17420, Forwards Semiannual fitness-for-duty Performance Data for Jan-June 1998,per 10CFR26.71(d)1998-08-31031 August 1998 Forwards Semiannual fitness-for-duty Performance Data for Jan-June 1998,per 10CFR26.71(d) CY-98-107, Forwards Decommissioning Cost Study for Connecticut Yankee Nuclear Power Plant. Adjustments to Cost Estimate Will Be Made as Necessary as Detailed Work Planning Progresses & Elements of Cost Estimate Periodically Reviewed & Updated1998-08-25025 August 1998 Forwards Decommissioning Cost Study for Connecticut Yankee Nuclear Power Plant. Adjustments to Cost Estimate Will Be Made as Necessary as Detailed Work Planning Progresses & Elements of Cost Estimate Periodically Reviewed & Updated B17384, Submits fitness-for-duty Program Rept for Investigations Re Unsatisfactory Performance Test Results,Per 10CFR26,App a, Subpart B,Section 2.8(e)(4).No New Commitments Are Contained in Ltr1998-08-20020 August 1998 Submits fitness-for-duty Program Rept for Investigations Re Unsatisfactory Performance Test Results,Per 10CFR26,App a, Subpart B,Section 2.8(e)(4).No New Commitments Are Contained in Ltr CY-98-141, Requests Postponement of Defueled Emergency Plan Exercise Until 980923.Ltr Contains No New Commitments1998-08-13013 August 1998 Requests Postponement of Defueled Emergency Plan Exercise Until 980923.Ltr Contains No New Commitments CY-98-145, Provides Remediation Plans for Offsite Location 9621.Work Associated W/Location 9621 Scheduled to Begin on 9808171998-08-13013 August 1998 Provides Remediation Plans for Offsite Location 9621.Work Associated W/Location 9621 Scheduled to Begin on 980817 CY-98-132, Provides NRC W/Addl Info on Plant Defueled Emergency Plan. Util Stores Resin Liners Inside Area Protected by Vehicle Barriers1998-07-31031 July 1998 Provides NRC W/Addl Info on Plant Defueled Emergency Plan. Util Stores Resin Liners Inside Area Protected by Vehicle Barriers CY-98-127, Provides Clarifying Info Re Spent Fuel Pool make-up Capability at Hnp.Conclusions Reached by NRC Staff in SER Contained in Issuance of License Amend 193 Not Impacted & & Remain Valid1998-07-30030 July 1998 Provides Clarifying Info Re Spent Fuel Pool make-up Capability at Hnp.Conclusions Reached by NRC Staff in SER Contained in Issuance of License Amend 193 Not Impacted & & Remain Valid CY-98-118, Informs NRC Staff That Rev 38 to Plant Emergency Plan Has Been Implemented1998-07-21021 July 1998 Informs NRC Staff That Rev 38 to Plant Emergency Plan Has Been Implemented CY-98-121, Responds to NRC Request for Addl Info on Recent Operational Events at Plant.Corrective Actions That Have Been Taken, Discussed1998-07-16016 July 1998 Responds to NRC Request for Addl Info on Recent Operational Events at Plant.Corrective Actions That Have Been Taken, Discussed ML20151Z0221998-07-10010 July 1998 Informs That R Bassilakis & Gejdenson Share Same Concerns Re Recent Incidents at Connecticut Yankee Reactor in Haddam Neck,Ct & Hope That NRC Address Concerns Promptly ML20236P0971998-07-0909 July 1998 Inquires About Truth of Cyap Having No Shift Compliment of Licensed Operators at Haddam Neck Reactor ML20239A0651998-07-0707 July 1998 Discusses 980620 Inadvertent Radwaste Discharge from Plant Reactor.Team of NRC Inspectors,Completely Independent of Region I,Requested to Investigate Region I Ability to Regulate Effectively 1999-09-02
[Table view] Category:UTILITY TO NRC
MONTHYEARB13622, Forwards Crdr Human Engineering Discrepancy Info for Plant1990-08-30030 August 1990 Forwards Crdr Human Engineering Discrepancy Info for Plant B13617, Requests NRC Revise Confirmatory Order for Plant to Specify New Completion Date of Cycle 16 Refueling Outage for Item II.E.1.2.Util Intends to Implement Design Change During Next Refueling Outage to Resolve Listed Issues1990-08-22022 August 1990 Requests NRC Revise Confirmatory Order for Plant to Specify New Completion Date of Cycle 16 Refueling Outage for Item II.E.1.2.Util Intends to Implement Design Change During Next Refueling Outage to Resolve Listed Issues B13615, Requests That 900705 Request for Amend to License DPR-61 Be Approved on Emergency Basis & That Temporary Waiver of Compliance from Tech Spec 4.4.6.2.1.g Be Given Until NRC Acts on Emergency Amend1990-08-20020 August 1990 Requests That 900705 Request for Amend to License DPR-61 Be Approved on Emergency Basis & That Temporary Waiver of Compliance from Tech Spec 4.4.6.2.1.g Be Given Until NRC Acts on Emergency Amend B13611, Forwards, Semiannual Radioactive Effluents Release Rept for Jan-June 19901990-08-16016 August 1990 Forwards, Semiannual Radioactive Effluents Release Rept for Jan-June 1990 B13595, Notifies NRC That Utils Volunteer to Participate in Emergency Response Data Sys Project for All Four Nuclear Units,Per Generic Ltr 89-15 & NUREG-13941990-08-14014 August 1990 Notifies NRC That Utils Volunteer to Participate in Emergency Response Data Sys Project for All Four Nuclear Units,Per Generic Ltr 89-15 & NUREG-1394 B13602, Submits Addendum to Plant Control Room Design Review Summary Rept,Per .Lists 10CFR50 App R-related Mods Outside Control Room That Could Not Be Reviewed Until After Final Implementation of Changes1990-08-14014 August 1990 Submits Addendum to Plant Control Room Design Review Summary Rept,Per .Lists 10CFR50 App R-related Mods Outside Control Room That Could Not Be Reviewed Until After Final Implementation of Changes B13580, Discusses Revised Tech Spec Conversion Program,Reflecting Conversion of Tech Spec to Westinghouse Sts.Future Upgrade of Tech Specs Should Be Conducted on Voluntary Basis Consistent W/Nrc Policy Statement1990-08-10010 August 1990 Discusses Revised Tech Spec Conversion Program,Reflecting Conversion of Tech Spec to Westinghouse Sts.Future Upgrade of Tech Specs Should Be Conducted on Voluntary Basis Consistent W/Nrc Policy Statement B13603, Withdraws 900731 Request for Temporary Waiver of Compliance W/Tech Spec 3.7.1.2 Re Inoperability of Auxiliary Feedwater Pumps1990-08-0202 August 1990 Withdraws 900731 Request for Temporary Waiver of Compliance W/Tech Spec 3.7.1.2 Re Inoperability of Auxiliary Feedwater Pumps B13601, Requests Temporary Waiver of Compliance from Tech Spec 3.7.1.2,allowing Plant to Remain in Mode 3 for Addl 14 Days Beyond Current Action Statement Limits W/One or of Two Auxiliary Feedwater Pumps Inoperable1990-07-31031 July 1990 Requests Temporary Waiver of Compliance from Tech Spec 3.7.1.2,allowing Plant to Remain in Mode 3 for Addl 14 Days Beyond Current Action Statement Limits W/One or of Two Auxiliary Feedwater Pumps Inoperable B13585, Provides Supplemental Response to Generic Ltr 89-19 Re Request for Action Concerning Resolution of Unresolved Safety Issue A-47.Plant Procedures Modified to Provide Operability Verification of Steam Generator Protection Sys1990-07-26026 July 1990 Provides Supplemental Response to Generic Ltr 89-19 Re Request for Action Concerning Resolution of Unresolved Safety Issue A-47.Plant Procedures Modified to Provide Operability Verification of Steam Generator Protection Sys B13571, Clarifies 900625 Tech Spec Change Request Re Limit of 160 Failed Fuel Rods for Cycle 16 Operation1990-07-19019 July 1990 Clarifies 900625 Tech Spec Change Request Re Limit of 160 Failed Fuel Rods for Cycle 16 Operation B13569, Forwards, Haddam Neck Plant Decommissioning Financial Assurance Certification Rept1990-07-18018 July 1990 Forwards, Haddam Neck Plant Decommissioning Financial Assurance Certification Rept ML20055E6791990-07-0606 July 1990 Responds to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs. All Socket Welded Joints from Header Isolation motor-operated Valves to RCS for All 4 Loops Examined.No Recordable Indications Found ML20055D3461990-07-0303 July 1990 Responds to NRC Bulletin 90-001 Re Loss of Fill Oil Transmitters Mfg by Rosemount.Operability Determinations Performed & Documented for All Rosemount 1153 & 1154 Transmitters at Facility ML20055D7191990-06-29029 June 1990 Amends 900604 Rev 13 to QA Program B13564, Provides NRC W/Info Re Plant Pressurizer as follow-up to 900607 Meeting.Info Particularly Concerns Disposition of Three Indications on Pressurizer Inner Surface & Discussion of Resolution of Previous Indication1990-06-29029 June 1990 Provides NRC W/Info Re Plant Pressurizer as follow-up to 900607 Meeting.Info Particularly Concerns Disposition of Three Indications on Pressurizer Inner Surface & Discussion of Resolution of Previous Indication B13550, Responds to Generic Ltr 90-04, Request for Info on Status of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Implementation & Completion Tables for staff-imposed Requirements Encl1990-06-27027 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Implementation & Completion Tables for staff-imposed Requirements Encl B13364, Forwards Rev 19 to Modified Amended Security Plan.Rev Withheld (Ref 10CFR2.790(a))1989-10-0505 October 1989 Forwards Rev 19 to Modified Amended Security Plan.Rev Withheld (Ref 10CFR2.790(a)) B13376, Forwards Util Response to Generic Ltr 89-04 Re Guidance on Developing Acceptable Inservice Test Programs1989-10-0202 October 1989 Forwards Util Response to Generic Ltr 89-04 Re Guidance on Developing Acceptable Inservice Test Programs A08598, Provides Clarification of Util Position Re Emergency Notification Sys (ENS) & Health Physics Network (Hpn).Util Intends to Provide Two Separate Qualified Individuals for ENS & HPN Communications During Exercise Drills1989-10-0202 October 1989 Provides Clarification of Util Position Re Emergency Notification Sys (ENS) & Health Physics Network (Hpn).Util Intends to Provide Two Separate Qualified Individuals for ENS & HPN Communications During Exercise Drills B13375, Responds to Request for Addl Info Re Electrical Distribution Sys Design Associated W/New Switchgear Bldg.New Switchgear Bldg Provides Opportunity to Minimize Dependence on Motor Control Ctr 5 & Further Reduce Level of Risk1989-09-29029 September 1989 Responds to Request for Addl Info Re Electrical Distribution Sys Design Associated W/New Switchgear Bldg.New Switchgear Bldg Provides Opportunity to Minimize Dependence on Motor Control Ctr 5 & Further Reduce Level of Risk ML20248E4521989-09-29029 September 1989 Forwards Proposed Tech Spec Pages Omitted from 890728 Application for Amend to License DPR-61 Re Cycle 16 Reload B13374, Forwards Bimonthly Progress Rept 18 Re New Switchgear Bldg Const1989-09-27027 September 1989 Forwards Bimonthly Progress Rept 18 Re New Switchgear Bldg Const B13352, Requests Exemption from Certain Requirements of 10CFR50,App J to Assure That Containment Leakage During Design Basis Event Will Not Exceed Applicable Leakage Limits. Justification Encl1989-09-0808 September 1989 Requests Exemption from Certain Requirements of 10CFR50,App J to Assure That Containment Leakage During Design Basis Event Will Not Exceed Applicable Leakage Limits. Justification Encl A08170, Forwards Updated Schedules for Operator Licensing & Requalification Exams for Plants,Per Generic Ltrs 89-12 & 89-031989-08-30030 August 1989 Forwards Updated Schedules for Operator Licensing & Requalification Exams for Plants,Per Generic Ltrs 89-12 & 89-03 B13346, Forwards Tornado Missile Risk Analysis of Bleed & Feed & Auxiliary Feedwater Safe Shutdown Sys at Connecticut Yankee Atomic Power Station, Per SEP Topics III-2 & III-4.A1989-08-30030 August 1989 Forwards Tornado Missile Risk Analysis of Bleed & Feed & Auxiliary Feedwater Safe Shutdown Sys at Connecticut Yankee Atomic Power Station, Per SEP Topics III-2 & III-4.A B13351, Provides Clarifications of Util & NRC 890525 Insp Rept 50-213/89-200.Util Proposes to Extend Schedule for Completion of Sampling and Evaluation Program to 900930 & Valves That Fail Systematic Testing Will Be Replaced1989-08-28028 August 1989 Provides Clarifications of Util & NRC 890525 Insp Rept 50-213/89-200.Util Proposes to Extend Schedule for Completion of Sampling and Evaluation Program to 900930 & Valves That Fail Systematic Testing Will Be Replaced A08237, Confirms Receipt of Listed Invoices for Costs Incurred During Routine Insps1989-08-28028 August 1989 Confirms Receipt of Listed Invoices for Costs Incurred During Routine Insps B13340, Submits Results of Svc Water & Primary Auxiliary Bldg Equipment Operability Analyses Not Provided in 890428 Submittal of Results of ECCS Single Failure Analysis1989-08-24024 August 1989 Submits Results of Svc Water & Primary Auxiliary Bldg Equipment Operability Analyses Not Provided in 890428 Submittal of Results of ECCS Single Failure Analysis A08211, Ack Receipt of Listed Invoices for Cost Incurred During Routine Insps at Plants.Payment Will Be Made on 8909061989-08-22022 August 1989 Ack Receipt of Listed Invoices for Cost Incurred During Routine Insps at Plants.Payment Will Be Made on 890906 B13341, Forwards WCAP-12196, Svc Water Sys Design Basis Temp Increase to 95 F for Connecticut Yankee & Haddam Neck Plant, Per Request in Amend 112 to License DPR-61.Northeast Utils Svc Co Suppl to Rept Also Encl1989-08-21021 August 1989 Forwards WCAP-12196, Svc Water Sys Design Basis Temp Increase to 95 F for Connecticut Yankee & Haddam Neck Plant, Per Request in Amend 112 to License DPR-61.Northeast Utils Svc Co Suppl to Rept Also Encl B13339, Forwards Addl Info Re Util 881026 & 890306 Revised Tech Specs Requests,Per NRC Request.Existing 8 H Shift Frequency Does Not Provide Enough Latitude within 8 H Shift Whereas 12 H Shift Would1989-08-21021 August 1989 Forwards Addl Info Re Util 881026 & 890306 Revised Tech Specs Requests,Per NRC Request.Existing 8 H Shift Frequency Does Not Provide Enough Latitude within 8 H Shift Whereas 12 H Shift Would B13342, Provides Util Position Re Procurement of non-code Class Fasteners in ASME Code Class Applications from Mfg or Matl Suppliers,Per Util to NRC & Insp Rept 50-423/88-18.App B Program Assures Use of Equivalent Items1989-08-15015 August 1989 Provides Util Position Re Procurement of non-code Class Fasteners in ASME Code Class Applications from Mfg or Matl Suppliers,Per Util to NRC & Insp Rept 50-423/88-18.App B Program Assures Use of Equivalent Items A08186, Ack Receipt of Listed Invoices for Cost Incurred During Insps.Funds Will Be wire-transferred on 8908241989-08-0808 August 1989 Ack Receipt of Listed Invoices for Cost Incurred During Insps.Funds Will Be wire-transferred on 890824 B13336, Forwards Annual Occupational Exposure Rept 19881989-08-0808 August 1989 Forwards Annual Occupational Exposure Rept 1988 ML20247Q7691989-08-0303 August 1989 Forwards Rev 12 to QA Program Topical Rept B13323, Comments on Draft Reg Guide, Assuring Availability of Funds for Decommissioning Nuclear Reactors. Changes to Stated Phrases Re Certification Amounts Discussed1989-08-0303 August 1989 Comments on Draft Reg Guide, Assuring Availability of Funds for Decommissioning Nuclear Reactors. Changes to Stated Phrases Re Certification Amounts Discussed A08153, Advises That Payment for Invoices H1386,H1387,H1410 & H1411 Will Be wire-transferred on 890810,per NRC Instructions1989-08-0101 August 1989 Advises That Payment for Invoices H1386,H1387,H1410 & H1411 Will Be wire-transferred on 890810,per NRC Instructions B13321, Informs of Inability to Submit plant-specific Analyses for Util as Planned,Due to Delays Encountered in Completing Sensitivity & Break Spectrum Analysis.Meeting Between NRC & Util Representatives Arranged for 8908101989-08-0101 August 1989 Informs of Inability to Submit plant-specific Analyses for Util as Planned,Due to Delays Encountered in Completing Sensitivity & Break Spectrum Analysis.Meeting Between NRC & Util Representatives Arranged for 890810 A07974, Advises That No Agreements Restricting Employees to Inform NRC of Potential Safety Issues Exist,Per V Stello1989-07-31031 July 1989 Advises That No Agreements Restricting Employees to Inform NRC of Potential Safety Issues Exist,Per V Stello ML20248B7931989-07-31031 July 1989 Forwards Response to NRC Request for Addl Info Re Util 890421 Application for Amend to License DPR-61,revising Tech Spec 3.6, Eccs. Revised Tech Spec Also Encl B13307, Responds to Generic Ltr 89-06, Task Action Plan Item I.D.2 - SPDS - 10CFR50.54(f). SPDS for Plants Meet Applicable Requirements of Suppl 1 to NUREG-0737 & Consistent W/ Majority of Positions Provided in NUREG-13421989-07-21021 July 1989 Responds to Generic Ltr 89-06, Task Action Plan Item I.D.2 - SPDS - 10CFR50.54(f). SPDS for Plants Meet Applicable Requirements of Suppl 1 to NUREG-0737 & Consistent W/ Majority of Positions Provided in NUREG-1342 A08037, Responds to Generic Ltr 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning. Plants Have Programs & Procedures in Place to Monitor Erosion/Corrosion for Both single-phase & two-phase Flow Sys1989-07-13013 July 1989 Responds to Generic Ltr 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning. Plants Have Programs & Procedures in Place to Monitor Erosion/Corrosion for Both single-phase & two-phase Flow Sys A08007, Requests Extension of Deadline for Response to Generic Ltr 89-06, Task Action Plan Item I.D.2-SPDS-10CFR50.54(f), to No Later than 890721.Addl Time Needed to Allow for Completion of Thorough Internal Review of Response1989-07-12012 July 1989 Requests Extension of Deadline for Response to Generic Ltr 89-06, Task Action Plan Item I.D.2-SPDS-10CFR50.54(f), to No Later than 890721.Addl Time Needed to Allow for Completion of Thorough Internal Review of Response B13282, Forwards Response to 890501 Request for Addl Info Re Util Const of New Switchgear Bldg at Plant1989-07-10010 July 1989 Forwards Response to 890501 Request for Addl Info Re Util Const of New Switchgear Bldg at Plant A08093, Advises That Fourth Quarterly Installment of 1989 Annual Fees Will Be Wire Transferred on 890731 in Payment of Invoices H1146,H1222,H1190 & H1151,per 10CFR1711989-07-0707 July 1989 Advises That Fourth Quarterly Installment of 1989 Annual Fees Will Be Wire Transferred on 890731 in Payment of Invoices H1146,H1222,H1190 & H1151,per 10CFR171 A08111, Advises That Payment for 10CFR170 Fee Sent to Jm Rodriquez Re NRC Review of Rev 11 to QA Topical Rept1989-07-0707 July 1989 Advises That Payment for 10CFR170 Fee Sent to Jm Rodriquez Re NRC Review of Rev 11 to QA Topical Rept A07951, Responds to Suppl 3 to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs. Issue Represents No Problem at Any Millstone Unit.Haddam Neck Valves Will Be Inspected for Leakage During Upcoming Refueling Outage1989-06-30030 June 1989 Responds to Suppl 3 to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs. Issue Represents No Problem at Any Millstone Unit.Haddam Neck Valves Will Be Inspected for Leakage During Upcoming Refueling Outage B13268, Submits Addl Info Re 890425 Proposed Rev to Tech Specs Administrative Controls Section Concerning High Radiation Areas,Per NRC 890505 Conference Call1989-06-26026 June 1989 Submits Addl Info Re 890425 Proposed Rev to Tech Specs Administrative Controls Section Concerning High Radiation Areas,Per NRC 890505 Conference Call B13215, Advises That One Technically Qualified & Trained Individual Per Site Will Man Health Physics Network & Emergency Notification Sys Telephone Lines at Plants,Per NRC Ltrs1989-06-23023 June 1989 Advises That One Technically Qualified & Trained Individual Per Site Will Man Health Physics Network & Emergency Notification Sys Telephone Lines at Plants,Per NRC Ltrs 1990-08-30
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N UTILITIES cenerei Ome.. . seiden street, Beriin. Connecticut oa = c"'
HARTFORD. CONNECTICUT 06141-0270 L L T; "","2'%','OC'. (203) ces-sooo September 29, 1989 Docket No. 50-213 B13375 Re: 10CFR50, Appendix R ISAP Topic 1.64 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:
Haddam Neck P1 ant Nce: Switchgear Building Response to Reouest for Additional Information On August 29, 1989, the NRC Staff and Connecticut Yankee Atomic Power Company (CYAPC0) conducted a telephone conference to discuss certain aspects of the electrical distribution system design associated with the New Switchgear Building at the Haddam Neck Plant. Specifically, this conference was held to discuss NRC Staff concerns related to the Semi-Vital AC Auto Bus Transfer (ABT) scheme between train "A" MCC 5 and train "B" MCC 12-11. At the conclusion of this conference, the NRC Staff requested that CYAPC0 provide a written response to the concerns addressed during this conference c all .
CYAPC0's response to this request for additional information is included in Attachment 1.
We trust you will find this information satisfactory and we remain available to answer any questions you may have.
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY r J E. J./Ir6czka // ~
Seni6r Vice President cc: W. T. Russell, Region I Administrator A. B. Wang, NRC Project Manager, Haddam Neck Plant J. T. Shedlosky, Senior Resident Inspector, Haddam Neck Plant f00I o
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8910100100 89D929 PDR ADDCK 05000213 P PNV l
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, Docket No. 50-213 B13375 Attachment 1 Haddam Neck Plant New Switchgear Building Response to Request for Additional Information September 1989
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Attachment 1 g B13375/Page 1
-September 29, 1989 Haddam Neck Plant Resoonse to Reauest for Additional Information NRC Ouestion The semi-vital AC distribution system modifications associated with the New Switchgear Building at the Haddam Neck Plant, include the installation of an Auto Bus Transfer (ABT) device between train "A" of MCC 5 and train "B" of MCC 12-11 which could potentially cross-tie these two trains during a faulted condition. This feature appears contrary to Safety Guide 1.6 guidelines, which disallow such a switching scheme.
CYAPC0 Response:
The original design of the Haddam Neck Plant did not include complete redun-dancy of electrical systems, and MCC 5 is the sole power supply to the 120-volt semi-vital AC distribution panels. In addition, MCC 5 is not train "A" dedicated, but can be aligned to either train "A" or "B" at the discretion of plant operators. Should the selected supply to MCC 5 fail, the MCC will auto transfer to the other division. This feature has been reviewed by the NRC Staff and found acceptable in the Staff's July 1, 1971 Safety Evaluation Report for the Haddam Neck Plant. This feature compensates for the lack of redundant load groups within certain systems.
The semi-vital AC (SVAC) system is being modified under the auspices of improvements being implemented to satisfy 10CFR50, Appendix R requirements.
The SVAC modifications of concern to the NRC Staff, although being accom-plished under this program, is not actually required to satisfy Appendix R but rather was initiated by CYAPC0 concurrently with the Appendix R' modifications to reduce core melt frequency via a reduction in transient initiation fre-quency.
The Haddam Neck Plant Probabilistic Safety Study (I) identified the loss of motor control center 5 (MCC 5) as a risk outlier. MCC 5 is the sole power supply to the 120V semi-vital AC distribution panels. Subsequently, a design modification to preclude damage to the centrifugal charging pumps given loss of MCC 5 or semi-vital power was implemented. An Emergency Operating Proce-dure (EOP) for the loss of MCC 5 was also implemented. An E0P for Total Loss of Semi-Vital Power had been in effect for some time.
(1) J. F. Opeka letter to C. I. Grimes, "Haddam Neck Plant Probabilistic Safety Study - Summary Report and Results," dated March 31, 1986. 1 l
1 Attachment 1 B13375/Page 2 September 29, 1989 l
l While loss ofthese MCC improvements 5, some residualhave risksignificant remains.f g) reduced the level of risk from Two major consequences of the loss of semi-vital power include:
o trip of both main feedwater pumps after 14 second delay on low suction pressure signal.
o loss of control power for the pressurizer PORVs necessary for feed and bleed.
Therefore, two of three means for decay heat removal would be lost. The third means, Auxiliary Feedwater, would be potentially available.
The new switchgear building provides the opportunity to minimize the depen-dence on MCC 5 and further reduce the level of risk. Under Integrated Safety Assessment Program (ISAP) Topic 1.64 " System Dependencies on MCC 5," an assessment is on-going of potential design changes whereby redundant equipment would be repowered from sources other than MCC 5.
For the reasons noted above, the semi-vital power system has been identified as a very important system which is totally dependent on MCC 5. It is desir-able to provide a source of power which is physically and electrically inde-pendent of MCC 5. An alternate power supply for the semi-vital power system would increase the system reliability for random failure of MCC 5, tornado wind and missile concerns, and fire in the old switchgear room or cable spreading area.
Since MCC 12-11 is in the new switchgear building and is tornado protected, it is the logical choice for the alternate power supply for semi-vital power.
With careful consideration to the routing of electrical cables, substantial risk reduction for fire and tornado can be realized from the proposed alter-nate power supply. By repowering additional equipment (now on existing load centers and/or MCC 5) from the new 480-V load center and/or MCC 12-11, the capability to " feed and bleed" from equipment powered independently of MCC 5 could be realized.
In order to realize the full benefit of an alternate power source for semi-vital power, an essentially continuous power supply is necessary. The plant transient response to a total loss of semi-vital power is so rapid that there is insufficient time for operator action to prevent a total loss of main (2) E. J. Mroczka letter to U.S. Nuclear Regulatory Commission, " Response to Generic Letter 88-20--Individual Plant Examinations for Severe Accident Vulnerabilities," dated July 27, 1989.
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1 Attachment 1 B13375/Page 3 September 29, 1989 feedwater and reactor trip. The proposed auto bus transfer will preclude loss of semi-vital power as a result of a number of single failures in the 480V AC distribution system, such as a loss of MCC 5.
Based on insights from the existing Probabilistic Safety Study for internally initiated events, fire, and tornado winds and missiles, the proposed modifica-tion to the semi-vital power system is estimated to provide a 2 to 6 x 10 5/ year core melt frequency reduction. The benefit realized would depend on the extent to which other equipment currently on MCC 5 is repowered from the 480 VAC distribution center in the new switchgear building.
CYAPC0 has performed a failure analysis on the proposed modification to the SVAC system, and has concluded that the likelihood of a failure occurring which could cross-connect and result in failure of both train "A" and "B" components is extromely unlikely. In fact, five different failures would need to occur to tie MCC 5 and MCC 12-11 together. The following is a discussion of the failure analysis in support of this conclusion. A simplified one-line diagram is attached to aid in your review of this analysis.
o Failure #1 is a catastrophic failure of the electrically operated two pole-double throw ABT device. This failure can be assumed to result in faults to ground, bolted faults or a very improbable tying together of both of the ABT input sources of power. The probability of this failure is low since maximum fault current from the two sources is limited to 167 amps each , a level not likely to cause failures of a catastrophic nature. Furtner, due to the design of the device, it is not possible to manually tie the two sources of power together via the ABT as a result of operator error.
o Failure #2 is a failure of the MCC 12-11 connected Category 1E Regulating ,
Transformer to perform as specified, i.e., its inability to continuously I maintain its electrical integrity with a bolted fault on its secondary !
terminals while limiting primary current to less than full load. This i failure is considered highly unlikely because the transformer is a current limiting device. This has been documented by the manufacturer in the vendor supplied documentation as follows: l "when the load is increased beyond the transformer's rated !
value, a point is reached where the output voltage suddenly collapses and will not regain its normal value ;
until the load is at least partially released. Under a l direct short circuit, the load current is limited to l approximately 150-200% of the rated full load value, the input wattage to less than 10% of normal. A CVS will protect both itself and its load against damage from excessive fault currents. Fusing of load circuits is not necessary."
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A Attachment 1 l B13375/Page 4'
- September 29,~1989 ll o Failure #3 is that.of the MCC 12-11 30 ampere circuit breaker to remove
-the fault-precipitated by Failure #2 above. This breaker is coordinated with the MCC 12-11 supply breaker and, functioning as designed, would remove-the fault with minimal upset to the bus; however, we will assume that it fails and results in the loss of MCC 12-11, the "B" division MCC.
Note - (Thus.far, with three (3) failures, one division of safety related MCC power is lost.)
o Failure #4 is identical to #2 above except that it is experienced by the regulating transformer powered via MCC 5.
o Failure #5 is identical to #3 above except that it is experienced by the MCC 5 30 ampere circuit breaker.
The series of failures (5) required to tie the two buses (MCC 5 and 12-11) together is not considered credible. The benefits gained by this improvement to the SVAC system far outweigh the potential for reducing the availability of redundant MCC's. CYAPC0 viewed this issue more as a Regulatory Guide 1.75
" qualified. isolator" issue rather than a Safety Guide 1.6 issue, but agrees that a case could be reasonably made for either or both Guides being the governing criteria.
CYAPC0 is preparing a Regulatory Guide 1.75 Users Guide for the purpose of capturing design details and ensuring continued compliance with this Regu-latory Guide for future modifications using the new switchgear building and its connecting pathway as a source of power and/or cable routing. As request-ed by the NRC Staff during our telephone conference, CYAPC0 will provide a copy of this Users Guide to the Staff upon its completion.
Additionally, during our telephone conference the NRC Staff requested a write-up of the switching scheme for vital AC buses C and D along with supporting diagrams. CYAPC0willbeprovidetheNRCStaffwithtbisrequested information in a future submittal, expected to be submitted to the NRC by October.31, 1989, i
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- SIMPLIFIED DIAGRAM OF SVAC SCHEME ,
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489 Y MCC (A/B) 489 Y MCC 11 (B) b 30 A b 30 A W 19 WA W, la WA Q M Constant Uoltage Transformer Q Constant Voltage transformer l
V AUTOMATIC-BUS TRANSFER (ABT) DEVICE 4
v LEGEND SEMI-VITAL o A/B - A or B Train '
AC PANELS Operator 1 & 2 Selectable o B - B Train
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