|
---|
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 Amend Deletes Certain TSs Either No Longer Applicable to Permanently Shutdown & Defueled State of Reactor or Duplicate Regulatory Requirements CY-99-137, Notifies NRC of Intent to Apply Haddam Neck Plant 10CFR50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] |
Text
-
CONNECTICUT YANKEE AT O MIC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD e EAST HAMPToN. CT 06424-3099 October 14,1998 Docket No. 50-213 CY-98-129 Re: 10 CFR 2.206 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C 20555 Haddam Neck Plant Supplemental Response to 2.206 Petition Questions Soent Fuct Pool Cooling Methods The purpose of this letter is for Connecticut Yankee Atomic Power Company (CYAPCO) to provide supplemental information to its response to 2.206 petition questions originally provided by letter dated June 29,1998W, on behalf of the Haddam Neck Plant. The initial request for additional information was contained in an NRC letter dated May 28,1998(2) ,
Additional information, subsequently requested verbally by the NRC, is provided in this letter on the spent fuel pool cooling methods and cooling fan noise test results.
Attachment 1 to this letter restates the NRC questions and provides CYAPCO's supplemental response.
The following is CYAPCO's pending commitment made within this letter:
CY-98-129-01 Procedure AOP 3.2-59, " Loss of Spent Fuel Cooling" will be revised to \
provide the operators guidance on when to open and when to l subsequently close the SFB doors and roof hatch. The procedure will also direct the operators to request that airborne radioactivity surveys be performed when the SFB doors and roof hatch are opened.
- ] t.. O (1) CYAPCO Letter CY-98-103, from R. A. Mellor, to the U.S. Nuclear Regulatory Commission, " Response to 2.206 Petition Questions Spent Fuel Pool Cooling Methods",
dated June 29,1998.
(2) NRC Letter from Thomas L. Fredrichs, to Russell Mellor, " Request for Information - 2.206 Petition Regarding Spent Fuel Cooling Methods", dated May 28,1998.
9910190297 981014 PDR ADOCK 05000213 W PM ,
U. S. Nucl:cr Regulatory Commission-i-
CY-98-129/Page 2 L
If there are any question regarding this submittal, please contact Mr. G. P. van Noordennen at (860) 267-3938.
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY For: Russell A. Mellor Vice President - Operations and Decommissioning By: M 'e KeI1n'eth J. Heider '
Decommissioning Director Attachment cc: H. J. Miller, NRC Administrator, Region I i
~
l T. L. Fredrichs, NRC Project Manager, Haddam Neck Plant W. J. Raymond, NRC Senior Resident inspector, Haddam Neck Plant E. Wilds, Director, CT DEP Monitoring and Radiation Division l
l l
1 1 l 1
l l \
l i
I l 1 I l
. . . . .= - - - - . . . . - . . . . - -. . . . ..
. Docket Number 50-213 CY-98-129 s
-)
i Attachment 1 1 Haddam Neck Plant .
Supplemental Response to 2.206 Petition Questions Spent Fuel Pool Cooling Methods l
l 1
i October 1998
+
U. S. Nuclaar Regulatory Commission f ' CY-98-129/ Attachment 1/Page 1 l
.Question 1 .
. 1 Do you intend to use ventilation through open doors and roof hatches of the spent fuel g building (SFB) to cool the spent fuel pool (SFP) in the event forced cooling is unavailable? )
if yes, answer questions 2 through 6. If no, answer nuestion 6.
{s.
Response 1 - ;
I Yes. However, as discussed below, the need to open the SFB doors and roof hatch is j' extremely unlikely.
i' The heat energy in the st_ored spent fuel is released to the SFP water continuously. Part of this energy is released to the air above the SFP by evaporation of pool water. This occurs l' regardless of whether or not forced cooling is operating. The amount of water that
[ ' evaporates is a function of pool water temperature, air flow over the pool and the relative 3 humidity of the' air flowing over the pool. Vapor generated by evaporation of pool water is
- normally removed from the EFB by an exhaust fan into the discharge line of the Primary Auxiliary Building (PAB) purge fans. The PAB purge fan discharge line leads to the plant L stack, which is monitored for radiation.
L 1
The SFP island at the Haddam Neck Plant (HNP) will be comprised of two redundant SFP
- _ cooling subsystems.- Each SFP cooling subsystem will provide forced cooling for the SFP.
Each subsystem of the SFP cooling system will include a SFP cooling loop, an intermediate
!. . cooling loop and a spray cooling loop. The redundant subsystems of the SFP cooling loop and the intermediate cooling loop will have the capability to be crosstied, at the component level, to the other train to provide additional flexibility. Currently, all of the SFP cooling system equipment, as well as the SFB exhaust fan, can be powered from the EG-2B emergency diesel generator, which is independent from any off-site power supply. However,
. during phase ll of the SFP island project, a new diesel and switchgear will be installed to power SFP cooling loads in the event of loss of offsite power. Multiple failures of components would have to occur to result in the normal SFP island method of forced cooling not being available.
i l The intermediate loops have hose connections so that other sources of water can be used to
, cool the SFP heat exchangers. Temporary hoses and fittings are available on-site to make i- the backup cooling connection. Backup sources of water available include the fire system j which has a diesel engine driven pump that is not dependent on off-site power.
Should all the above permanent and temporary backup forced cooling equipment become unavailable, or all available power be lost to the SFP cooling pumps for an extended period of time, the heat energy from the fuel will cause the SFP temperature to rise until the heat
- removed from the SFP from evaporation is equal to the heat addition. This is calculated to L occur prior to the SFP reaching 170 F and would result in a maximum evaporation rate of
] approximately four gallons per minute. It is estimated to take approximately 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> to
- reach the existing Technical Specification pool temperature limit of 150 F, given an initial
- 0. S. Nucinar Regulatory Commission CY-98-129/ Attachment 1/Page 2 temperature in the SFP of 110 F. During this time, normal SFB ventilation, which will continue to direct the released vapor to a monitored stack, would continue to be used, if available.
The need to open the SFB doors and roof hatch, is extremely unlikely. It would take the long term loss of a number of normal and alternate spent fuel pool cooling methods to reach this point. Only during an event that would result in an extended loss of forced cooling, which would cause the fuel pool temperature to exceed the technical specification limit of 150 F, would the plant operators take action to open the SFB doors and roof hatch and allow the vapor to flow directly to the atmosphere outside the building. The Haddam Neck Plant has never experienced a loss of SFP cooling event that challenged the 150 degree SFP temperature limit in all its years of operation and it is not likely that this will occur in the future.
A review of past losses to spent fuel cooling either from a loss of off-site power or component malfunction confirm that cooling would be restored well within the estimated 50 hour5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> time frame.
The Defueled Emergency Plan will require the declaration of an " Unusual Event"if an uncontrolled heatup of the SFP occurs such that the bulk pool temperature exceeds 150 F. As such, the NRC will be notified and communications established under the Defueled Emergency Plan process. All action taken from that point on would be provided under associated supporting plant procedures with the NRC cognizant of the situation.
Make-up water to replenish the evaporated water is discussed in the response to question 2.
Monitoring of the vapor pathway is discussed in the response to question 4.
Question 2 l As the SFP water level drops, particulate material may deposit on the SFP walls. How has your dose consequence evaluation accounted for the potential release of particulate material?
Response 2 With the SFP isolated from the Reactor Cavity, the postulation of a continuous drop in water level within the SFP is not part of the Haddam Neck Plant's design basis. The Haddam Neck technical specifications require the SFP water level to be maintained at least 20 feet above the stored fuel. Alarms are present which will notify the operators if the water level above the top of the fuel would go above 20' 9" or below 20' 4" With the water level maintained above 20 feet, there will be no significant buildup of additional particulate matter to deposit on the spent fuel pool walls and thus, no new source of particulate activity would be released from the SFB.
U. S. Nuclear Regulatory Commission CY-98-129/ Attachment 1/Page 3 There_ are multiple sources of makeup water available ranging from demineralized water stored in multiple on-site tanks to river water. The tanks are the Demineralized Water Storage Tank (DWST), Primary Water Storage Tank (PWST), and the Recycled Primary Water Storage Tank (RPWST). However, the DWST is the designated seismically qualified make-up source. Two makeup sources (DWST and River Water) are available without the use of the off-site electric power supply, Assuming the maximum evaporation rate is approximately four gallons per minute, a minimum of three days supply of demineralized water is maintained on-site in a seismically qualified tank. If offsite power is available, the demineralized water supply can be replenished within 3 days. If offsite power is not available, alternate means of obtaining demineralized water would be evaluated. However, river water will also be available as a makeup supply, as necessary.
4
- The committed effective dose equivalent to an offsite member of the public due to potential -
. release of particulate radioactivity from the walls of the SFP, in the unlikely event of an uncontrolled loss of pool level to 13 feet above the top of the fuel assemblies, is approximately 1.1 E-3 mrem. The analysis which supports this dose equivalent includes many conservative assumptions regarding the transport of radioactive material from the contamination on the walls of the SFP to the environment. For example, the analysis assumes a release of material to the environment through an unfiltered pathway via an open roof vent. Additionally, the analysis assumes that an individualis present at the site boundary -
for the entire 2 week period during this postulated release condition. Two weeks is chosen as a conservative maximum amount of time it would take to restore the system or component which is postulated to fail. This analysis clearly indicates that the offsite dose to members of the public from this postulated release is bounded by the design basis accidents described in the HNP Final Safety Analysis Report.
In the highly unlikely event that an uncontrolled decrease in fuel pool level was 4
experienced with an inability for any of the makeup sources to replenish it, an Unusual Event would be declared. As such, the NRC would be notified and communications established under the Defueled Emergency Plan process. All action taken from that point on would be in accordance with associated supporting plant procedures with the NRC cognizant of the situation. Consideration would be given to close the SFB doors and roof hatch if the fuel would no longer be adequately shielded by water. It is estimated that 10 feet of water above the fuel would be needed to provide adequate shielding to plant emergency personnel. The 10 foot water depth exceeds the minimum water depth of 8 feet for shielding one year old fuel as specified by ANS!/ANS-57.7-1988, "American National Standard Design Criteria for an Independent Spent Fuel Storage installation (Water Pool Type)".
Question 3 What are the dose consequences of cooling the SFP by ventilating the SFB through open doors and the roof hatch under normal conditions and postulated design basis events?
_ . _ . . . _ . _ _ _ . _ _ _ _ _ . _ _ _ . _ _ _ . _ _ . _ . . . ~ . _ _ _ ._
U. S. Nuctur R gulatory Commi:sion CY-98-129/ Attachment 1/Page 4 Response 3 There is no normal condition under which the SFP is cooled by ventilating the SFB through
. open doors and the roof hatch.-
l l In the highly unlikely event of only evaporative cooling of the pool, the calculated total dose at the site boundary from the evaporation of the pool water for a fourteen day event is approximately 0.253 mrem. The analysis supporting this dose assumes a 5 gallon per minute evaporation rate. Tritium is the only radionuclide considered and the evaporated l water is discharged through the building roof vent unfiltered.
J l
Dose from particulate radioactivity discussed in answer to question 2 is not expected since the makeup water quantities are minimal and there are multiple methods of makeup.
l However, if the particulate dose (1.1 E-3 mrem) was added to the evaporation dose (0.253 mrem), the total dose would be only slightly increased to approximately 0.2541 mrem for a fourteen day event.
- Question 4 l 'What is your procedure for monitoring and quantifying a release of radioactive materials via I pathways through the open doors and roof hatch?
r Response 4 CYAPCO personnel would obtain samples using procedure RPM 2.5-12, " Airborne Radioactivity Surveys." The samples would be analyzed using plant procedures CHDP 2.3-14, ." Operation of the Canberra Genie Gamma Spectroscopy System" and CHDP 2.4-6,
" Tritium Analysis", to determine the specific activity of the released vapor. Total released activity would be determined using CHDP 6.4-2," Gaseous Discharge Data Handling (Hand Calculation)" and CHDP 6.4-4, " Particulate Discharge Data Handling (Hand Calculation)." As decommissioning progresses, these procedures will evolve and may be revised to support changing plant needs.
Question 5 L What action will be taken in the event that high radiation levels are detected emanating from the SFB, while the SFB is being ventilated through open doors and the roof hatch?
Response 5 I In the event high radiation levels are detected emanating from the SFB, while the SFB is being ventilated through open doors and the roof hatch, and consistent with our response to l question 2, consideration would be given to close the SFB doors and roof hatch. The SFB
- ventilation system effluent would be manually diverted to a filter if the ventilation system is
!- operable.
U. S. Nucl ar Rtgulatory Commission CY-98-129/ Attachment 1/Page 5 High levels of. radiation will not be released during this ventilation evolution since there is no mechanism for causing this type of release. Spent fuel will remain covered and cooled through established makeup sources and evaporative cooling. The only activity that could create a noticeable radiation release would be a fuel handling accident. However, AOP 3.2-59, " Loss of Spent Fuel Cocling", requires that work in progress in the spent fuel pool (including fuel handling) be stopped untilloss of cooling is resolved. Procedure NOP 2.15-3, " Spent Fuel Building Ventilation System Operation" contains a precaution that the SFB Exhaust Ventilation System shall be in service, with the exhaust fan suction aligned through the charcoal filter, when initiating fuel movement operations or crane movement above the spent fuel pool. In addition, technical specifications related to fuel handling require the fuel building ventilation to be in service. In any event, the accident analysis for the fuel handling accident in the SFB does not assume the ventilation system is operating during the event. Even without taking credit for ventilation, the off-site doses during this accident are well below the EPA Protective Action Guidelinesm as discussed in CYAPCO's letter dated May 30,1997(2)
Question 6 How will local noise levels be affected by the modified SFP cooling system?
Response 6 Noise levels have been monitored during testing for the new cooling system and were found to be well within Department of Environmental Protection (DEP) regulations. CYAPCO procured fans with reduced noise emission specifically to address this potential issue. Noise levels from the coolers located at the HNP are low because CYAPCO has only 4 fans which operate at a slow speed of 900 rpm. Operation at this slow speed reduces the noise.
CYAPCO has had an extensive sound level survey performed to verify that the noise level of the modified SFP cooling system will be in compliance with the DEP regulations. The contractor performing the survey not only confirmed that the noise levels were wel! within the DEP regulations, but stated that they believed the acoustic irnpact on the community would be negligible.
(1) EPA 400-R-92-001," Manual of Protective Actions Guides and Protective Actions for Nuclear Incidents," US EPA,1991.
(2) CYAPCO letter CY-97-047 from T. C. Feigenbaum to U. S. Nuclear Regulatory Commission, "Defueled Emergency Plan and Request For Exemption From 10CFR50.54(q) For Offstie Response," dated May 30,1997.