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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 Amend Deletes Certain TSs Either No Longer Applicable to Permanently Shutdown & Defueled State of Reactor or Duplicate Regulatory Requirements CY-99-137, Notifies NRC of Intent to Apply Haddam Neck Plant 10CFR50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 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 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 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 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 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 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
[Table view] |
Text
r --a CONNECTICUT YANKEE ATOMIC POWER COMPANY B E R L I N, CONNECTICUT P o Box 270 HARTFORD. CONNECTICUT 06141-0270 TELEPHONE 203-66s-5000 March 31,1986 Docket No. 50-213 B12020 Office of Nuclear Reactor Regulation Attn: Mr. Christopher I. Grimes, Director Integrated Safety Assessment Project Directorate Division of PWR Licensing - B U.S. Nuclear Regulatory Commission Washington, D.C. 20535 Gentlemen:
Haddam Neck Plant r
P_robabi'.istic Safety Study - Summary Report and Results Northeast Utilities Service Company (NUSCO), on behalf of Connecticut Yankee Atomic Power Company (CYAPCO), has recently completed a plant-specific Probabilistic Safety Study (PSS) including a Best Estimate LOCA Analysis for the Haddam Neck Plant. The studies have been and will be utilized for many purposes. Among the near-term applications for the PSS is for assistance in making backfitting decisions in the context of the Integrated Safety Assessment Program (ISAP) currently being implemented at the Haddam Neck Plant.
Background
During the past several years, NUSCO has been implementing a Living PRA Program for the nuclear plants within the Northeast Utilities (NU) system. The major element of this program is the development, maintenance and use of PRA models, of each of the system's nu:lcar power plants, for assistance in evaluating potential plant backfits and operating procedures modifications. The Living PRA Program affords us the flexibility to quickly and accurately analyze the impact 4 on plant safety of changes to the plant's design configuration and significant changes to operating procedures.
NUSCO has completed the development of a computerized PRA model of the Haddam Neck Plant. This model will be periodically updated to incorporate plant design changes, significant operational changes and relevant updated equipment performance data.
The Haddam Neck PSS utilized current state-of-the-art computational and modeling techniques. Included in the study were a comprehensive analysis of best estimate plant specific LOCA and transient response, Haddam Neck specific operating, reliability and maintenance data, the latest plant design 8604100283 860331 PDR N
P ADOCK OD000213 g PDR 1 1
. - - . ~ _ _
- 7 j changes and draf t symptom-oriented Emergency Operating Procedures. The scope 'of the PSS also included support system failure initiated events, 3
Interfacing system LOCA events and fire initiated events.(l) '
r r As noted in SECY-85-160,(2) the integrated assessment of the Haddam Neck
- Plant is scheduled to be completed during 1986. The schedule was based, in part, ;
- on our schedule for completion of and documentation of a summary report of the !
! - Haddam Neck PSS during March 1986. In keeping with the schedule for j completion of the integrated assessment, our submittal of the Haddam Neck PSS Summary Report and Best Estimate LOCA Analysis will enable the Staff to begin 4
i the probabilistic safety analysis review phase of the integrated assessment of ,
Haddam Neck. :
] Results i
j it is Northeast Utilities Corporate Policy to provide dependable and economic ,
i power to its customers, without endangering the health and safety of the public. ;
- As one element of achieving this policy, NU has set forth quantitative safety goals for the design and operation of our nuclear power plants. If it is '
4 determined that any one of our nuclear power plants does not' meet the !
} acceptance criteria as established by our safety goals, our policy is to_ take the ;
corrective action necessary to meet the criteria, on a schedule commensurate
~
with the level of deficiency found.
} The Haddam Neck PSS calculated a mean core melt frequency of 5.5 x 10-4 per j reactor-year for the Haddam Neck Plant which exceeds one of our safety goals.
! As a result, we have committed resources to work to decrease the overall core
! melt frequency at the Haddam Neck Plant. We have begun evaluating some of j the engineering insights obtained from the PSS, in order to determine the
- alternatives available to reduce the calculated core melt frequency. A summary .
! of the engineering insights obtained from the PSS and items we are evaluating to l j reduce the calculated core melt risk at the Haddam Neck Plant are contained in !
! Enclosure 2.
j As outlined in Enclosures 1 and 2, the PSS and Best Estimate 1.OCA Analysis ,
j yielded many insights into the operation of the plant including:
1 l o Containment heat removal is available for most core melt sequences. As t 1 the availability of containment heat removal is considered to be an 4
effective means of maintaining containment integrity and removing fission
- products to prevent large scale radioactive releases if core melt occurs, 1 the public risk impact of a majority of the dominant core melt sequences is j reduced by having containment heat removal available.
i
{
(I) The fire initiated events section of the PSS has not been completed at the present time. NUSCO will document and docket the updated results to the '
Staff following completion of the analysis. .,
(2) SECY-85-160, " Integrated Safety Assessment Program - Implementation 1 Plan," dated May 6,1985.
I 1 ,
I i
, e o An AC independent means of providing containment spray during a station blackout is provided by the diesel-driven fire pump. This feature is important in minimizing the offsite public consequences resulting from a core melt accident due to station blackout.
o Approximately 40% of the calculated core melt frequency at Haddam Neck is attributable to small and medium break LOCA scenarios. The PSS utilized LOCA frequencies which were derived from generic PWR data as presented in WASH-1400. As the Haddam Neck Plant utilizes austenitic stainless steel which has superior ductility toughness and resistance to brittle fracture compared to ferritic carbon steel used in many PWR
, plants, the actual Haddam Neck Plant LOCA frequency is expected to be lower.
}' o The Haddam Neck plant-specific control room simulator has been completed and is currently being used for operator training. This affords
- us the opportunity to improve the training of operators to respond to plant transient situations.
In light of the above, and our continuing efforts to identify, evaluate and when necessary implement procedural or hardware modifications to upgrade the i '
operation of the plant, CYAPCO has concluded that continued operation of the Haddam Neck Plant does not pose any undue risk to the public.
P i
Summary Report NUSCO has completed summary reports of the Haddam Neck PSS and Best Estimate LOCA) Analysis which we are providing to the Staff as an attachment to this letter.13 The PSS summary report is a comprehensive summary of the
- core melt frequencies for various sequences calculated in the study and the calculational methodologies and analysis techniques utilized in the development of the PRA model. The PSS summary report contains the items outilned belows i
i o Determination of Initiating Events System investigations
- Initiator frequency calculations o Accident Sequence Analysis
- Classification of event sequence outcomes
- Plant systems event tree models Plant support system event tree models I o Plant Systems Reliability Analysis ,
Plant component reliability data collection and analysis 1 Plant systems reliability modeling
! (3) The summary reports consist of the Haddam Neck Probabilistic Safety Study (Volumes 1-4) and the Best Estimate LOCA Analysis (one volume) for the Haddam Neck Plant.
1 1
l
t+ -
o Human Reliability Analysis
- Introduction and methodology
- Screening analysis
- Detailed representation of operator action
- Summary of results o Accident Sequence Quantification Matrix quantification
- Core melt accident sequence quantification results
- Containment heat removal reliability consideration In support of the PSS, a Best Estimate LOCA Analysis was performed concurrent with the development of the PSS models. The Best Estimate LOCA Analysis summary report describes the results of comprehensive plant specific accident analyses used to determine best estimate system success criteria, best estimate plant response to failed equipment and components, and time frames for operator recovery of failed systems. These calculations were performed using the NULAP 5 Code with best estimate input values. The Best Estimate LOCA Analysis contains analyses of the scenarios described belows o Station Blackout o incore Instrument Tube Rupture o Steam Generator Tube Rupture o Large Break LOCA o Medium Break LOCA o Small Break LOCA o Total Loss of Main and Auxiliary Feedwater with Feed and Bleed Cooling o Anticipated Transient Without Scram o Total Loss of DC Power In accordance with your request we are providing 26 copies of the PSS and Best Estimate LOCA Analysis to the ISAP Project Directorate for distribution within the NRC (including NRR, Region 1, ACRS, etc.).
In addition to the summary reports, we are providing the Staff with additional information on the scope and results of the PSS as outlined below.
o Enclosure 1 A summary of the results of the PSS is provided herein.
o Enclosure 2 Discussions of the major engineering insights NUSCO has obtained from the PSS Including the following two plant design changes already implemented at the plant are provided herein.
o Plant Design change to climinate the common dependence of emergency diesel generator cooling on Motor Control Center-5 (MCC-5). This dependence, found while doing the analysis, could j be significant during a loss of offsite power event as the diesel ,
generators are dependent on MCC-5 to maintain diesel generator cooling. However, the dies-1 generators are not dependent upon l I
. _ ~ . .
b
- h. .s .
l MCC-5 to start up followir>g a losrof offsite power event. If one or both diesel generators start-up, accept their emergency loads and properly reenergize - MCC-5 as designed, the original configuration would result'h, long-term dhsel generator cooling availability.
a l
. o Plant design change to mitigate the effects of the loss of MCC-5 i N,, (as an initiator) by tripping thgcharging pumps.
., s These design changes were. credited in our quantification of the PSS as a
, result of our preliminary evaluations of the PSS models which highlighted these design conditions as being potential significant contributors to the l total core melt frequency at the pt2nt.: ,
' Upcoming Activities 4 7' j
i I, .
i % in order to facilltate Staff review and understanding of the Haddam Neck PSS and to ensure that maximum utilization of the P55 is achieved,in ISAP and other applications, we are willing ts treet witin'yo1r Staff to review the PSS. Our . ;
efforts to date have focused on' completing a:A documenting this study, and on a limited number of high priord of the PSS. In the near terir.', we plan y issues whichand to complete were documentidentified during the our analysis of conduct fire initiated events and to evaluate the report in more detall to identify additional issues which warrant further study. Consistent with the overall ISAP framework, these issues will be identified, new ISAP topics will be proposed and they will be evaluated in a manner snsistent with the process in place for all other ISAP topics.
Very truly yours, ;
} s ; .. ;
Ti CONNF.CTICUT YANKEE ATOMIC POWER COMPANY ,
r
(
s " %1.\ F. Opeta 1.FAL. N i
Senior Vice President 3
cc: T. E. (Aurley, Region I (with Enclosures 1 and 2 only) -
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