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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K3161999-10-19019 October 1999 Forwards Amend 195 to License DPR-61 & Safety Evaluation. Amend Deletes Certain TSs Either No Longer Applicable to Permanently Shutdown & Defueled State of Reactor or Duplicate Regulatory Requirements CY-99-137, Notifies NRC of Intent to Apply Haddam Neck Plant 10CFR50 App B,Qa Program to Activities Related to Development of ISFSI at Haddam1999-10-12012 October 1999 Notifies NRC of Intent to Apply Haddam Neck Plant 10CFR50 App B,Qa Program to Activities Related to Development of ISFSI at Haddam DD-99-11, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-11) Expired & That Commission Declined Any Review.Decision Became Final Action on 9910041999-10-0808 October 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-11) Expired & That Commission Declined Any Review.Decision Became Final Action on 991004 ML20212L1261999-10-0404 October 1999 Forwards Viewgraphs Presented by Licensee at 990923 Meeting with Nrc,In Response to Request ML20212D0341999-09-20020 September 1999 Expresses Appreciation for Accepting NRC Request for Tour of Haddam Neck Facility During on 991014.Invites R Mellor to Participate in NRC 1999 Decommissioninng Power Reactor Work- Shop:Nrc Insp Program at Decommissioning Power Reactors CY-99-111, Submits Clarification of Changes Made to Connecticut Yankee QA Program,Per Util 990810 Submittal.Change Will Be Submitted to NRC in Dec 1999 as Part of Annual Update1999-09-0202 September 1999 Submits Clarification of Changes Made to Connecticut Yankee QA Program,Per Util 990810 Submittal.Change Will Be Submitted to NRC in Dec 1999 as Part of Annual Update ML20211E8051999-08-20020 August 1999 Forwards Insp Rept 50-213/99-02 on 990420-0719.No Violations Noted.Completion of Corrective Actions for Spent Fuel Bldg Ventilation Issues Adequate ML20210J6021999-08-0202 August 1999 Informs That Info Re Orise Technical Survey Assistance to NRC at CT Yankee Is to Include Copies of Listed Documents CY-99-048, Forwards Cyap Rept CY-HP-0031,Rev 0, Bounding Dose Assessment for Offsite Radioactive Matls1999-07-29029 July 1999 Forwards Cyap Rept CY-HP-0031,Rev 0, Bounding Dose Assessment for Offsite Radioactive Matls CY-99-066, Forwards Revised Plan for Recovery of Licensed Matl from Offsite Locations.Completion of Implementation of Plan During Summer of 1999 Is Planned,Contingent on Support Extended by Property Owners,Weather & Uncontrolled Factors1999-07-20020 July 1999 Forwards Revised Plan for Recovery of Licensed Matl from Offsite Locations.Completion of Implementation of Plan During Summer of 1999 Is Planned,Contingent on Support Extended by Property Owners,Weather & Uncontrolled Factors ML20210C1491999-07-0101 July 1999 Responds to ,Which Responded to NRC Ltr & NOV & Informs That Engagement in Any Similar Wrongdoing in Future May Result in More Significant Enforcement Action. No Further Action Will Be Taken at This Time ML20209C3911999-06-30030 June 1999 Forwards TS Page 6-3 for Haddam Neck Plant ML20195H1741999-06-15015 June 1999 Forwards Original & Copy of Request for Approval of Certain Indirect & Direct Transfer of License & Ownership Interests of Montaup Electric Co (Montaup) with Respect to Nuclear Facilities Described as Listed ML20195F9011999-06-0909 June 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp 50-213/98-06 on 990226. Util Did Not Agree with Disposition of Issue Cited as Severity Level IV Violation.Violation Will Be Noncited ML20195H3591999-06-0202 June 1999 Responds to NRC Re Violations Noted in Insp of License DPR-61.Corrective Actions:Disciplinary Actions Were Taken by Util Against Jm Foley & Individual & Departmental Emphasis Is Placed on New HP Stds & Expectations ML20207E9031999-06-0202 June 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Mt Masnik Will Be Section Chief for Haddam Neck.Organization Chart Encl ML20207B9301999-05-25025 May 1999 Responds to 990114 Correspondence Re Changes to Plant Defueled Physical Security Plan Rev 1 Submitted Under 10CFR50.54(p).Implementation of Changes Subj to Insp to Confirm Changes Have Not Decreased Security Plan ML20207G1761999-05-21021 May 1999 Forwards Insp Rept 50-213/99-01 on 980119-990419 & Closure of CAL 1-97-010.No Violations Noted.Conduct of Activities Associated with Control of Radiological Work at Haddam Neck Generally Characterized as Careful & Thorough ML20206R7221999-05-12012 May 1999 Refers to Investigation 1-97-031 on 970616-0718 & Forwards Nov.Investigation Found That Recipient Deliberately Did Not Follow Radiation Protection Procedures,Falsified Documents & Provided Incomplete & Inaccurate Info to NRC ML20206R7021999-05-12012 May 1999 Refers to Investigation 1-97-008 Conducted by Region I & Forwards Notice of Violation.Investigation Found That Recipient Deliberately Attempted to Conceal Release of Contaminated Video Equipment ML20206R8051999-05-12012 May 1999 Responds to 3 Investigations,Repts 1-97-031,008 & 1-98-008 Between 970314 & 980722 as Well as Insp Conducted Between 980720 & 1102.Forwards Synopsis of 3rd OI Investigation ML20206J2801999-04-30030 April 1999 Forwards 1998 Annual Financial Repts for CT Light & Power Co,Western Ma Electric Co,Public Svc Co of Nh,North Atlantic Energy Corp,Northeast Nuclear Energy Co & North Atlantic Energy Svc Corp,License Holders CY-99-057, Forwards 1998 Annual Radioactive Effluent Rept for HNP, & Rev 10 to Remodcm. with Summary of Quantities of Solid Radwaste & Liquid & Gaseous Effluents,As Well as Summary of Assessment of Max Individual Dose1999-04-30030 April 1999 Forwards 1998 Annual Radioactive Effluent Rept for HNP, & Rev 10 to Remodcm. with Summary of Quantities of Solid Radwaste & Liquid & Gaseous Effluents,As Well as Summary of Assessment of Max Individual Dose ML20206C8631999-04-28028 April 1999 Forwards Amend 194 to License DPR-61 & Safety Evaluation. Amend Authorizes Relocation of Requirements Related to Seismic Monitoring Instrumentation from TSs to Technical Requirements Manual ML20206A6871999-04-22022 April 1999 Informs of Completion of Review of Re Nepco in Capacity as Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee Atomic Power Co ML20210V5221999-04-0808 April 1999 Discusses Continued Performance of Technical Assistance Activities for NRC & Environ Survey & Site Assessment Program (Essap) Survey Assistance at Cy IR 05000213/19960121999-04-0505 April 1999 Discusses NRC Insp Repts 50-213/96-12 & 50-213/98-04 on 961102-27 Re Airborne Radioactivity Contamination Event That Occurred in Fuel Transfer Canal & Reactor Cavity in Nov 1996.Notice of Violation Encl ML20205J7931999-04-0505 April 1999 Discusses NRC Insp Repts 50-213/96-12 & 50-213/98-04 on 961102-27 Re Airborne Radioactivity Contamination Event That Occurred in Fuel Transfer Canal & Reactor Cavity in Nov 1996.Notice of Violation Encl CY-99-042, Provides Info on Status of Decommissioning Funding for Haddam Neck Plant1999-03-31031 March 1999 Provides Info on Status of Decommissioning Funding for Haddam Neck Plant ML20206A6951999-03-29029 March 1999 Request Confirmation That No NRC Action or Approval,Required Relative to Proposed Change in Upstream Economic Ownership of New England Power Co,Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee CY-99-024, Responds to Violations Noted in Insp Rept 50-213/98-06. Corrective Actions:Meetings Were Held with Contractor Mgt, Disciplinary Action Against Worker Was Taken & Notices Alerting Workers to HRA Controls Were Posted1999-03-29029 March 1999 Responds to Violations Noted in Insp Rept 50-213/98-06. Corrective Actions:Meetings Were Held with Contractor Mgt, Disciplinary Action Against Worker Was Taken & Notices Alerting Workers to HRA Controls Were Posted B17697, Notifies NRC of Amount of Property Insurance Coverage, Effective 990401,for HNP & Mnps,Units 1,2 & 3,per Provisions of 10CFR50.54(w)1999-03-12012 March 1999 Notifies NRC of Amount of Property Insurance Coverage, Effective 990401,for HNP & Mnps,Units 1,2 & 3,per Provisions of 10CFR50.54(w) CY-99-032, Clarifies Info Re TRM Change Submitted with Re Proposed Rev to TSs on Seismic Monitoring1999-03-0909 March 1999 Clarifies Info Re TRM Change Submitted with Re Proposed Rev to TSs on Seismic Monitoring ML20207B6641999-02-26026 February 1999 Forwards Insp Rept 50-213/98-06 on 981103-990118 & Notice of Violation Re Locked High Radiation Area Doors That Were Found Unlocked by Staff.Security Program Was Also Inspected ML20204C6901999-02-22022 February 1999 Informs That Public Citizen Waives Copyright for 5th Edition of Nuclear Lemon So NRC May Reproduce for Purpose of Contributing to NRC Recommended Improvements to Oversight Process for Nuclear Power Reactors ML20203H9621999-02-17017 February 1999 Responds to to Dk Rathbun Which Forwarded Number of Questions from Constituent Re Spent Fuel Decommissioned Nuclear plants.NUREG-1628, Staff Responses to Frequently Asked Questions Re Decommissioning of NPPs Encl.W/O Encl CY-99-005, Responds to NRC 981221 RAI Re Amend 193 to License to Reflect Permanent Shutdown Condition of Plant.Licensee Withdrawing 981030 (CY-98-199) Request & Will Submit Corrections in Future Proposed Rev to TS1999-01-29029 January 1999 Responds to NRC 981221 RAI Re Amend 193 to License to Reflect Permanent Shutdown Condition of Plant.Licensee Withdrawing 981030 (CY-98-199) Request & Will Submit Corrections in Future Proposed Rev to TS CY-99-023, Provides Summary of Understandings Reached During 990108 Meeting Between Util & CT Dept of Environ Protection Re Dike Area Rainwater Reporting Protocol1999-01-28028 January 1999 Provides Summary of Understandings Reached During 990108 Meeting Between Util & CT Dept of Environ Protection Re Dike Area Rainwater Reporting Protocol ML20203H9711999-01-21021 January 1999 Requests Response to Concerns Raised by Constitutent M Marucci Re Spent Fuel at Decommissioned Nuclear Plants CY-99-002, Forwards Response to NRC 981203 RAI Re Proposed License Amend to Relocate Requirements for Seismic Monitoring Instrumentation from Section 3/4.3.3.3 of TS to Trm. Supporting TSs Encl1999-01-18018 January 1999 Forwards Response to NRC 981203 RAI Re Proposed License Amend to Relocate Requirements for Seismic Monitoring Instrumentation from Section 3/4.3.3.3 of TS to Trm. Supporting TSs Encl CY-99-010, Provides Special Rept Concerning Potential of Radiation Exposure Due to Hypothetical Explosive Attack to Facility. Without Encl1999-01-14014 January 1999 Provides Special Rept Concerning Potential of Radiation Exposure Due to Hypothetical Explosive Attack to Facility. Without Encl CY-99-009, Forwards Rev 1 to Haddam Neck Plant Defueled Physical Security Plan,Per 10CFR50.54(p).Rev Does Not Decrease Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 & 2.7901999-01-14014 January 1999 Forwards Rev 1 to Haddam Neck Plant Defueled Physical Security Plan,Per 10CFR50.54(p).Rev Does Not Decrease Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 & 2.790 ML20206R6051999-01-11011 January 1999 Ack Receipt of Submiting Sf Mgt Plan.Staff Has Reviewed Plan & Notes Plan to Store Sf in SFP Until DOE Takes Physical Possession of Fuel DD-98-12, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision DD-98-12 Has Expired.Decision Became Final Agency Action on 981211. with Certificate of Svc.Served on 9812221998-12-22022 December 1998 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision DD-98-12 Has Expired.Decision Became Final Agency Action on 981211. with Certificate of Svc.Served on 981222 CY-98-142, Forwards Proposed Rev 2 of Cyap QAP for Info & Approval of Exception Number 8 of App E of Cy Qap.Copy of Rev 2 Showing Changes from Rev 1 Also Included1998-12-22022 December 1998 Forwards Proposed Rev 2 of Cyap QAP for Info & Approval of Exception Number 8 of App E of Cy Qap.Copy of Rev 2 Showing Changes from Rev 1 Also Included ML20198R1321998-12-21021 December 1998 Forwards Insp Rept 50-213/98-05 on 980720-1102.No Violations Noted.Insp Completes Review of Licensee Actions Described in ,In Response to NOV & Proposed Imposition of Civil Penalties ML20198K8651998-12-21021 December 1998 Ack Receipt of ,Requesting Corrected Pages to Be Issued for License Amend 193,issued on 980630.Informs That Inconsistencies Found When Comparing Corrected Pages Submitted on 981030 & License Amend Application CY-98-201, Provides Clarification of NRC Staff SE for Amend 193 Which Approved HNP Defueled TSs1998-12-0303 December 1998 Provides Clarification of NRC Staff SE for Amend 193 Which Approved HNP Defueled TSs IR 05000213/19980041998-11-27027 November 1998 Forwards Special Insp Rept 50-213/98-04 of Licensee Performance During Reactor Coolant Sys Chemical Decontamination ML20195J3571998-11-19019 November 1998 Forwards Exemption from Certain Requirements of 10CFR50.54(w) & 10CFR140.Exemption Submitted in Response to 971007 Application & Suppls & 1218,requesting Reduction in Amount of Insurance Required for Facility 1999-09-20
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARCY-99-137, Notifies NRC of Intent to Apply Haddam Neck Plant 10CFR50 App B,Qa Program to Activities Related to Development of ISFSI at Haddam1999-10-12012 October 1999 Notifies NRC of Intent to Apply Haddam Neck Plant 10CFR50 App B,Qa Program to Activities Related to Development of ISFSI at Haddam CY-99-111, Submits Clarification of Changes Made to Connecticut Yankee QA Program,Per Util 990810 Submittal.Change Will Be Submitted to NRC in Dec 1999 as Part of Annual Update1999-09-0202 September 1999 Submits Clarification of Changes Made to Connecticut Yankee QA Program,Per Util 990810 Submittal.Change Will Be Submitted to NRC in Dec 1999 as Part of Annual Update CY-99-048, Forwards Cyap Rept CY-HP-0031,Rev 0, Bounding Dose Assessment for Offsite Radioactive Matls1999-07-29029 July 1999 Forwards Cyap Rept CY-HP-0031,Rev 0, Bounding Dose Assessment for Offsite Radioactive Matls CY-99-066, Forwards Revised Plan for Recovery of Licensed Matl from Offsite Locations.Completion of Implementation of Plan During Summer of 1999 Is Planned,Contingent on Support Extended by Property Owners,Weather & Uncontrolled Factors1999-07-20020 July 1999 Forwards Revised Plan for Recovery of Licensed Matl from Offsite Locations.Completion of Implementation of Plan During Summer of 1999 Is Planned,Contingent on Support Extended by Property Owners,Weather & Uncontrolled Factors ML20209C3911999-06-30030 June 1999 Forwards TS Page 6-3 for Haddam Neck Plant ML20195H1741999-06-15015 June 1999 Forwards Original & Copy of Request for Approval of Certain Indirect & Direct Transfer of License & Ownership Interests of Montaup Electric Co (Montaup) with Respect to Nuclear Facilities Described as Listed ML20195H3591999-06-0202 June 1999 Responds to NRC Re Violations Noted in Insp of License DPR-61.Corrective Actions:Disciplinary Actions Were Taken by Util Against Jm Foley & Individual & Departmental Emphasis Is Placed on New HP Stds & Expectations CY-99-057, Forwards 1998 Annual Radioactive Effluent Rept for HNP, & Rev 10 to Remodcm. with Summary of Quantities of Solid Radwaste & Liquid & Gaseous Effluents,As Well as Summary of Assessment of Max Individual Dose1999-04-30030 April 1999 Forwards 1998 Annual Radioactive Effluent Rept for HNP, & Rev 10 to Remodcm. with Summary of Quantities of Solid Radwaste & Liquid & Gaseous Effluents,As Well as Summary of Assessment of Max Individual Dose ML20206J2801999-04-30030 April 1999 Forwards 1998 Annual Financial Repts for CT Light & Power Co,Western Ma Electric Co,Public Svc Co of Nh,North Atlantic Energy Corp,Northeast Nuclear Energy Co & North Atlantic Energy Svc Corp,License Holders ML20210V5221999-04-0808 April 1999 Discusses Continued Performance of Technical Assistance Activities for NRC & Environ Survey & Site Assessment Program (Essap) Survey Assistance at Cy CY-99-042, Provides Info on Status of Decommissioning Funding for Haddam Neck Plant1999-03-31031 March 1999 Provides Info on Status of Decommissioning Funding for Haddam Neck Plant ML20206A6951999-03-29029 March 1999 Request Confirmation That No NRC Action or Approval,Required Relative to Proposed Change in Upstream Economic Ownership of New England Power Co,Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee CY-99-024, Responds to Violations Noted in Insp Rept 50-213/98-06. Corrective Actions:Meetings Were Held with Contractor Mgt, Disciplinary Action Against Worker Was Taken & Notices Alerting Workers to HRA Controls Were Posted1999-03-29029 March 1999 Responds to Violations Noted in Insp Rept 50-213/98-06. Corrective Actions:Meetings Were Held with Contractor Mgt, Disciplinary Action Against Worker Was Taken & Notices Alerting Workers to HRA Controls Were Posted B17697, Notifies NRC of Amount of Property Insurance Coverage, Effective 990401,for HNP & Mnps,Units 1,2 & 3,per Provisions of 10CFR50.54(w)1999-03-12012 March 1999 Notifies NRC of Amount of Property Insurance Coverage, Effective 990401,for HNP & Mnps,Units 1,2 & 3,per Provisions of 10CFR50.54(w) CY-99-032, Clarifies Info Re TRM Change Submitted with Re Proposed Rev to TSs on Seismic Monitoring1999-03-0909 March 1999 Clarifies Info Re TRM Change Submitted with Re Proposed Rev to TSs on Seismic Monitoring ML20204C6901999-02-22022 February 1999 Informs That Public Citizen Waives Copyright for 5th Edition of Nuclear Lemon So NRC May Reproduce for Purpose of Contributing to NRC Recommended Improvements to Oversight Process for Nuclear Power Reactors CY-99-005, Responds to NRC 981221 RAI Re Amend 193 to License to Reflect Permanent Shutdown Condition of Plant.Licensee Withdrawing 981030 (CY-98-199) Request & Will Submit Corrections in Future Proposed Rev to TS1999-01-29029 January 1999 Responds to NRC 981221 RAI Re Amend 193 to License to Reflect Permanent Shutdown Condition of Plant.Licensee Withdrawing 981030 (CY-98-199) Request & Will Submit Corrections in Future Proposed Rev to TS ML20203H9711999-01-21021 January 1999 Requests Response to Concerns Raised by Constitutent M Marucci Re Spent Fuel at Decommissioned Nuclear Plants CY-99-002, Forwards Response to NRC 981203 RAI Re Proposed License Amend to Relocate Requirements for Seismic Monitoring Instrumentation from Section 3/4.3.3.3 of TS to Trm. Supporting TSs Encl1999-01-18018 January 1999 Forwards Response to NRC 981203 RAI Re Proposed License Amend to Relocate Requirements for Seismic Monitoring Instrumentation from Section 3/4.3.3.3 of TS to Trm. Supporting TSs Encl CY-99-009, Forwards Rev 1 to Haddam Neck Plant Defueled Physical Security Plan,Per 10CFR50.54(p).Rev Does Not Decrease Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 & 2.7901999-01-14014 January 1999 Forwards Rev 1 to Haddam Neck Plant Defueled Physical Security Plan,Per 10CFR50.54(p).Rev Does Not Decrease Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 & 2.790 CY-99-010, Provides Special Rept Concerning Potential of Radiation Exposure Due to Hypothetical Explosive Attack to Facility. Without Encl1999-01-14014 January 1999 Provides Special Rept Concerning Potential of Radiation Exposure Due to Hypothetical Explosive Attack to Facility. Without Encl CY-98-142, Forwards Proposed Rev 2 of Cyap QAP for Info & Approval of Exception Number 8 of App E of Cy Qap.Copy of Rev 2 Showing Changes from Rev 1 Also Included1998-12-22022 December 1998 Forwards Proposed Rev 2 of Cyap QAP for Info & Approval of Exception Number 8 of App E of Cy Qap.Copy of Rev 2 Showing Changes from Rev 1 Also Included CY-98-201, Provides Clarification of NRC Staff SE for Amend 193 Which Approved HNP Defueled TSs1998-12-0303 December 1998 Provides Clarification of NRC Staff SE for Amend 193 Which Approved HNP Defueled TSs CY-98-191, Provides Notification That Util Implemented Defueled Emergency Plan for HNP on 981001.Util Completed Annual Exercise Required by Subj Plan & 10CFR50.471998-11-0505 November 1998 Provides Notification That Util Implemented Defueled Emergency Plan for HNP on 981001.Util Completed Annual Exercise Required by Subj Plan & 10CFR50.47 CY-98-140, Provides Commitment to Maintain Water Chemistry Requirements in HNP Technical Requirements Manual1998-11-0202 November 1998 Provides Commitment to Maintain Water Chemistry Requirements in HNP Technical Requirements Manual CY-98-183, Forwards Revised License Amend 193 TS Pages to Correct Amend Number on Pages Not Changed by Amend 193.No Commitments Contained within Ltr1998-10-30030 October 1998 Forwards Revised License Amend 193 TS Pages to Correct Amend Number on Pages Not Changed by Amend 193.No Commitments Contained within Ltr CY-98-199, Forwards Listing of Corrections Made & Revised Pages for Proposed License Amend 193.Ltr Also Transmits Repaginated Pages for TS Index & Section 1,per Request of NRC Project Manager1998-10-30030 October 1998 Forwards Listing of Corrections Made & Revised Pages for Proposed License Amend 193.Ltr Also Transmits Repaginated Pages for TS Index & Section 1,per Request of NRC Project Manager CY-98-062, Updates Info of Historical Nature in Response to Both NRC Historical Review Rept & NRC Insp Rept 50-213/97-11 Open Items1998-10-28028 October 1998 Updates Info of Historical Nature in Response to Both NRC Historical Review Rept & NRC Insp Rept 50-213/97-11 Open Items CY-98-154, Forwards Sf Mgt Plan for Haddam Neck Plant.Plan Submits Info on Mgt & Funding for Program to Safely Store Sf Following Permanent Cessation of Power Operations Until Title Is Transferred to DOE1998-10-28028 October 1998 Forwards Sf Mgt Plan for Haddam Neck Plant.Plan Submits Info on Mgt & Funding for Program to Safely Store Sf Following Permanent Cessation of Power Operations Until Title Is Transferred to DOE CY-98-129, Provides Supplemental Info to 980629 Response to 2.206 Petition Questions on Spent Fuel Cooling Methods.Util Pending Commitment Made within Ltr Stated1998-10-14014 October 1998 Provides Supplemental Info to 980629 Response to 2.206 Petition Questions on Spent Fuel Cooling Methods.Util Pending Commitment Made within Ltr Stated CY-98-186, Provides Notification of Organizational Changes Which Affect Cyap.Organization Chart,Biographical Profile of K Heider & Revised Distribution List for NRC Correspondence,Encl1998-10-0202 October 1998 Provides Notification of Organizational Changes Which Affect Cyap.Organization Chart,Biographical Profile of K Heider & Revised Distribution List for NRC Correspondence,Encl CY-98-153, Forwards Final Response to NRC 961009 RAI Re Configuration Mgt Project at Plant.No New Commitments Made within Ltr or Attachment1998-09-30030 September 1998 Forwards Final Response to NRC 961009 RAI Re Configuration Mgt Project at Plant.No New Commitments Made within Ltr or Attachment CY-98-157, Responds to NRC Request That Cyap Submit Proposed License Amend to Include Fuel Storage Pool Water Chemistry Program within Haddam Neck Plant Ts.Cyap Considers That Amend Is Not Necessary for Listed Reasons.Procedure Encl1998-09-28028 September 1998 Responds to NRC Request That Cyap Submit Proposed License Amend to Include Fuel Storage Pool Water Chemistry Program within Haddam Neck Plant Ts.Cyap Considers That Amend Is Not Necessary for Listed Reasons.Procedure Encl B17440, Corrects Errors in Ltrs & 980225 Re semi-annual Fitness for Duty Performance Data for Jan-June 1998 & July-Dec 19971998-09-24024 September 1998 Corrects Errors in Ltrs & 980225 Re semi-annual Fitness for Duty Performance Data for Jan-June 1998 & July-Dec 1997 CY-98-151, Responds to NRC Re Violations Noted in Insp Rept 50-213/98-03.Corrective Actions:Root Cause Team Has Determined That Shift Managers Initial Reportability Decision Was Not Correct1998-09-21021 September 1998 Responds to NRC Re Violations Noted in Insp Rept 50-213/98-03.Corrective Actions:Root Cause Team Has Determined That Shift Managers Initial Reportability Decision Was Not Correct ML20153G3891998-09-14014 September 1998 Informs That Union of Concerned Scientists Fully Supports Citizens Awareness Network Petition Filed Pursuant to 10CFR2.206,seeking to Revoke or Suspend License for Haddam Neck Nuclear Plant ML20154J9861998-09-11011 September 1998 Forwards for Service Upon Lj Callan,Jc Hoyle & Commission, Request for NRC to Revoke Connecticut Yankee Atomic Power Co License to Operate Haddam Neck Reactor Pursuant to 10CFR2.206 ML20154J9991998-09-11011 September 1998 Requests NRC Take Immediate Action to Revoke Util License to Operate Haddam Neck Nuclear Power Station Pursuant to 10CFR2.206 B17420, Forwards Semiannual fitness-for-duty Performance Data for Jan-June 1998,per 10CFR26.71(d)1998-08-31031 August 1998 Forwards Semiannual fitness-for-duty Performance Data for Jan-June 1998,per 10CFR26.71(d) CY-98-107, Forwards Decommissioning Cost Study for Connecticut Yankee Nuclear Power Plant. Adjustments to Cost Estimate Will Be Made as Necessary as Detailed Work Planning Progresses & Elements of Cost Estimate Periodically Reviewed & Updated1998-08-25025 August 1998 Forwards Decommissioning Cost Study for Connecticut Yankee Nuclear Power Plant. Adjustments to Cost Estimate Will Be Made as Necessary as Detailed Work Planning Progresses & Elements of Cost Estimate Periodically Reviewed & Updated B17384, Submits fitness-for-duty Program Rept for Investigations Re Unsatisfactory Performance Test Results,Per 10CFR26,App a, Subpart B,Section 2.8(e)(4).No New Commitments Are Contained in Ltr1998-08-20020 August 1998 Submits fitness-for-duty Program Rept for Investigations Re Unsatisfactory Performance Test Results,Per 10CFR26,App a, Subpart B,Section 2.8(e)(4).No New Commitments Are Contained in Ltr CY-98-141, Requests Postponement of Defueled Emergency Plan Exercise Until 980923.Ltr Contains No New Commitments1998-08-13013 August 1998 Requests Postponement of Defueled Emergency Plan Exercise Until 980923.Ltr Contains No New Commitments CY-98-145, Provides Remediation Plans for Offsite Location 9621.Work Associated W/Location 9621 Scheduled to Begin on 9808171998-08-13013 August 1998 Provides Remediation Plans for Offsite Location 9621.Work Associated W/Location 9621 Scheduled to Begin on 980817 CY-98-132, Provides NRC W/Addl Info on Plant Defueled Emergency Plan. Util Stores Resin Liners Inside Area Protected by Vehicle Barriers1998-07-31031 July 1998 Provides NRC W/Addl Info on Plant Defueled Emergency Plan. Util Stores Resin Liners Inside Area Protected by Vehicle Barriers CY-98-127, Provides Clarifying Info Re Spent Fuel Pool make-up Capability at Hnp.Conclusions Reached by NRC Staff in SER Contained in Issuance of License Amend 193 Not Impacted & & Remain Valid1998-07-30030 July 1998 Provides Clarifying Info Re Spent Fuel Pool make-up Capability at Hnp.Conclusions Reached by NRC Staff in SER Contained in Issuance of License Amend 193 Not Impacted & & Remain Valid CY-98-118, Informs NRC Staff That Rev 38 to Plant Emergency Plan Has Been Implemented1998-07-21021 July 1998 Informs NRC Staff That Rev 38 to Plant Emergency Plan Has Been Implemented CY-98-121, Responds to NRC Request for Addl Info on Recent Operational Events at Plant.Corrective Actions That Have Been Taken, Discussed1998-07-16016 July 1998 Responds to NRC Request for Addl Info on Recent Operational Events at Plant.Corrective Actions That Have Been Taken, Discussed ML20151Z0221998-07-10010 July 1998 Informs That R Bassilakis & Gejdenson Share Same Concerns Re Recent Incidents at Connecticut Yankee Reactor in Haddam Neck,Ct & Hope That NRC Address Concerns Promptly ML20236P0971998-07-0909 July 1998 Inquires About Truth of Cyap Having No Shift Compliment of Licensed Operators at Haddam Neck Reactor ML20239A0651998-07-0707 July 1998 Discusses 980620 Inadvertent Radwaste Discharge from Plant Reactor.Team of NRC Inspectors,Completely Independent of Region I,Requested to Investigate Region I Ability to Regulate Effectively 1999-09-02
[Table view] Category:UTILITY TO NRC
MONTHYEARB13622, Forwards Crdr Human Engineering Discrepancy Info for Plant1990-08-30030 August 1990 Forwards Crdr Human Engineering Discrepancy Info for Plant B13617, Requests NRC Revise Confirmatory Order for Plant to Specify New Completion Date of Cycle 16 Refueling Outage for Item II.E.1.2.Util Intends to Implement Design Change During Next Refueling Outage to Resolve Listed Issues1990-08-22022 August 1990 Requests NRC Revise Confirmatory Order for Plant to Specify New Completion Date of Cycle 16 Refueling Outage for Item II.E.1.2.Util Intends to Implement Design Change During Next Refueling Outage to Resolve Listed Issues B13615, Requests That 900705 Request for Amend to License DPR-61 Be Approved on Emergency Basis & That Temporary Waiver of Compliance from Tech Spec 4.4.6.2.1.g Be Given Until NRC Acts on Emergency Amend1990-08-20020 August 1990 Requests That 900705 Request for Amend to License DPR-61 Be Approved on Emergency Basis & That Temporary Waiver of Compliance from Tech Spec 4.4.6.2.1.g Be Given Until NRC Acts on Emergency Amend B13611, Forwards, Semiannual Radioactive Effluents Release Rept for Jan-June 19901990-08-16016 August 1990 Forwards, Semiannual Radioactive Effluents Release Rept for Jan-June 1990 B13595, Notifies NRC That Utils Volunteer to Participate in Emergency Response Data Sys Project for All Four Nuclear Units,Per Generic Ltr 89-15 & NUREG-13941990-08-14014 August 1990 Notifies NRC That Utils Volunteer to Participate in Emergency Response Data Sys Project for All Four Nuclear Units,Per Generic Ltr 89-15 & NUREG-1394 B13602, Submits Addendum to Plant Control Room Design Review Summary Rept,Per .Lists 10CFR50 App R-related Mods Outside Control Room That Could Not Be Reviewed Until After Final Implementation of Changes1990-08-14014 August 1990 Submits Addendum to Plant Control Room Design Review Summary Rept,Per .Lists 10CFR50 App R-related Mods Outside Control Room That Could Not Be Reviewed Until After Final Implementation of Changes B13580, Discusses Revised Tech Spec Conversion Program,Reflecting Conversion of Tech Spec to Westinghouse Sts.Future Upgrade of Tech Specs Should Be Conducted on Voluntary Basis Consistent W/Nrc Policy Statement1990-08-10010 August 1990 Discusses Revised Tech Spec Conversion Program,Reflecting Conversion of Tech Spec to Westinghouse Sts.Future Upgrade of Tech Specs Should Be Conducted on Voluntary Basis Consistent W/Nrc Policy Statement B13603, Withdraws 900731 Request for Temporary Waiver of Compliance W/Tech Spec 3.7.1.2 Re Inoperability of Auxiliary Feedwater Pumps1990-08-0202 August 1990 Withdraws 900731 Request for Temporary Waiver of Compliance W/Tech Spec 3.7.1.2 Re Inoperability of Auxiliary Feedwater Pumps B13601, Requests Temporary Waiver of Compliance from Tech Spec 3.7.1.2,allowing Plant to Remain in Mode 3 for Addl 14 Days Beyond Current Action Statement Limits W/One or of Two Auxiliary Feedwater Pumps Inoperable1990-07-31031 July 1990 Requests Temporary Waiver of Compliance from Tech Spec 3.7.1.2,allowing Plant to Remain in Mode 3 for Addl 14 Days Beyond Current Action Statement Limits W/One or of Two Auxiliary Feedwater Pumps Inoperable B13585, Provides Supplemental Response to Generic Ltr 89-19 Re Request for Action Concerning Resolution of Unresolved Safety Issue A-47.Plant Procedures Modified to Provide Operability Verification of Steam Generator Protection Sys1990-07-26026 July 1990 Provides Supplemental Response to Generic Ltr 89-19 Re Request for Action Concerning Resolution of Unresolved Safety Issue A-47.Plant Procedures Modified to Provide Operability Verification of Steam Generator Protection Sys B13571, Clarifies 900625 Tech Spec Change Request Re Limit of 160 Failed Fuel Rods for Cycle 16 Operation1990-07-19019 July 1990 Clarifies 900625 Tech Spec Change Request Re Limit of 160 Failed Fuel Rods for Cycle 16 Operation B13569, Forwards, Haddam Neck Plant Decommissioning Financial Assurance Certification Rept1990-07-18018 July 1990 Forwards, Haddam Neck Plant Decommissioning Financial Assurance Certification Rept ML20055E6791990-07-0606 July 1990 Responds to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs. All Socket Welded Joints from Header Isolation motor-operated Valves to RCS for All 4 Loops Examined.No Recordable Indications Found ML20055D3461990-07-0303 July 1990 Responds to NRC Bulletin 90-001 Re Loss of Fill Oil Transmitters Mfg by Rosemount.Operability Determinations Performed & Documented for All Rosemount 1153 & 1154 Transmitters at Facility 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 ML20055D7191990-06-29029 June 1990 Amends 900604 Rev 13 to QA Program B13550, Responds to Generic Ltr 90-04, Request for Info on Status of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Implementation & Completion Tables for staff-imposed Requirements Encl1990-06-27027 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Implementation & Completion Tables for staff-imposed Requirements Encl B13364, Forwards Rev 19 to Modified Amended Security Plan.Rev Withheld (Ref 10CFR2.790(a))1989-10-0505 October 1989 Forwards Rev 19 to Modified Amended Security Plan.Rev Withheld (Ref 10CFR2.790(a)) B13376, Forwards Util Response to Generic Ltr 89-04 Re Guidance on Developing Acceptable Inservice Test Programs1989-10-0202 October 1989 Forwards Util Response to Generic Ltr 89-04 Re Guidance on Developing Acceptable Inservice Test Programs A08598, Provides Clarification of Util Position Re Emergency Notification Sys (ENS) & Health Physics Network (Hpn).Util Intends to Provide Two Separate Qualified Individuals for ENS & HPN Communications During Exercise Drills1989-10-0202 October 1989 Provides Clarification of Util Position Re Emergency Notification Sys (ENS) & Health Physics Network (Hpn).Util Intends to Provide Two Separate Qualified Individuals for ENS & HPN Communications During Exercise Drills B13375, Responds to Request for Addl Info Re Electrical Distribution Sys Design Associated W/New Switchgear Bldg.New Switchgear Bldg Provides Opportunity to Minimize Dependence on Motor Control Ctr 5 & Further Reduce Level of Risk1989-09-29029 September 1989 Responds to Request for Addl Info Re Electrical Distribution Sys Design Associated W/New Switchgear Bldg.New Switchgear Bldg Provides Opportunity to Minimize Dependence on Motor Control Ctr 5 & Further Reduce Level of Risk ML20248E4521989-09-29029 September 1989 Forwards Proposed Tech Spec Pages Omitted from 890728 Application for Amend to License DPR-61 Re Cycle 16 Reload B13374, Forwards Bimonthly Progress Rept 18 Re New Switchgear Bldg Const1989-09-27027 September 1989 Forwards Bimonthly Progress Rept 18 Re New Switchgear Bldg Const B13352, Requests Exemption from Certain Requirements of 10CFR50,App J to Assure That Containment Leakage During Design Basis Event Will Not Exceed Applicable Leakage Limits. Justification Encl1989-09-0808 September 1989 Requests Exemption from Certain Requirements of 10CFR50,App J to Assure That Containment Leakage During Design Basis Event Will Not Exceed Applicable Leakage Limits. Justification Encl A08170, Forwards Updated Schedules for Operator Licensing & Requalification Exams for Plants,Per Generic Ltrs 89-12 & 89-031989-08-30030 August 1989 Forwards Updated Schedules for Operator Licensing & Requalification Exams for Plants,Per Generic Ltrs 89-12 & 89-03 B13346, Forwards Tornado Missile Risk Analysis of Bleed & Feed & Auxiliary Feedwater Safe Shutdown Sys at Connecticut Yankee Atomic Power Station, Per SEP Topics III-2 & III-4.A1989-08-30030 August 1989 Forwards Tornado Missile Risk Analysis of Bleed & Feed & Auxiliary Feedwater Safe Shutdown Sys at Connecticut Yankee Atomic Power Station, Per SEP Topics III-2 & III-4.A B13351, Provides Clarifications of Util & NRC 890525 Insp Rept 50-213/89-200.Util Proposes to Extend Schedule for Completion of Sampling and Evaluation Program to 900930 & Valves That Fail Systematic Testing Will Be Replaced1989-08-28028 August 1989 Provides Clarifications of Util & NRC 890525 Insp Rept 50-213/89-200.Util Proposes to Extend Schedule for Completion of Sampling and Evaluation Program to 900930 & Valves That Fail Systematic Testing Will Be Replaced A08237, Confirms Receipt of Listed Invoices for Costs Incurred During Routine Insps1989-08-28028 August 1989 Confirms Receipt of Listed Invoices for Costs Incurred During Routine Insps B13340, Submits Results of Svc Water & Primary Auxiliary Bldg Equipment Operability Analyses Not Provided in 890428 Submittal of Results of ECCS Single Failure Analysis1989-08-24024 August 1989 Submits Results of Svc Water & Primary Auxiliary Bldg Equipment Operability Analyses Not Provided in 890428 Submittal of Results of ECCS Single Failure Analysis A08211, Ack Receipt of Listed Invoices for Cost Incurred During Routine Insps at Plants.Payment Will Be Made on 8909061989-08-22022 August 1989 Ack Receipt of Listed Invoices for Cost Incurred During Routine Insps at Plants.Payment Will Be Made on 890906 B13341, Forwards WCAP-12196, Svc Water Sys Design Basis Temp Increase to 95 F for Connecticut Yankee & Haddam Neck Plant, Per Request in Amend 112 to License DPR-61.Northeast Utils Svc Co Suppl to Rept Also Encl1989-08-21021 August 1989 Forwards WCAP-12196, Svc Water Sys Design Basis Temp Increase to 95 F for Connecticut Yankee & Haddam Neck Plant, Per Request in Amend 112 to License DPR-61.Northeast Utils Svc Co Suppl to Rept Also Encl B13339, Forwards Addl Info Re Util 881026 & 890306 Revised Tech Specs Requests,Per NRC Request.Existing 8 H Shift Frequency Does Not Provide Enough Latitude within 8 H Shift Whereas 12 H Shift Would1989-08-21021 August 1989 Forwards Addl Info Re Util 881026 & 890306 Revised Tech Specs Requests,Per NRC Request.Existing 8 H Shift Frequency Does Not Provide Enough Latitude within 8 H Shift Whereas 12 H Shift Would B13342, Provides Util Position Re Procurement of non-code Class Fasteners in ASME Code Class Applications from Mfg or Matl Suppliers,Per Util to NRC & Insp Rept 50-423/88-18.App B Program Assures Use of Equivalent Items1989-08-15015 August 1989 Provides Util Position Re Procurement of non-code Class Fasteners in ASME Code Class Applications from Mfg or Matl Suppliers,Per Util to NRC & Insp Rept 50-423/88-18.App B Program Assures Use of Equivalent Items A08186, Ack Receipt of Listed Invoices for Cost Incurred During Insps.Funds Will Be wire-transferred on 8908241989-08-0808 August 1989 Ack Receipt of Listed Invoices for Cost Incurred During Insps.Funds Will Be wire-transferred on 890824 B13336, Forwards Annual Occupational Exposure Rept 19881989-08-0808 August 1989 Forwards Annual Occupational Exposure Rept 1988 ML20247Q7691989-08-0303 August 1989 Forwards Rev 12 to QA Program Topical Rept B13323, Comments on Draft Reg Guide, Assuring Availability of Funds for Decommissioning Nuclear Reactors. Changes to Stated Phrases Re Certification Amounts Discussed1989-08-0303 August 1989 Comments on Draft Reg Guide, Assuring Availability of Funds for Decommissioning Nuclear Reactors. Changes to Stated Phrases Re Certification Amounts Discussed A08153, Advises That Payment for Invoices H1386,H1387,H1410 & H1411 Will Be wire-transferred on 890810,per NRC Instructions1989-08-0101 August 1989 Advises That Payment for Invoices H1386,H1387,H1410 & H1411 Will Be wire-transferred on 890810,per NRC Instructions B13321, Informs of Inability to Submit plant-specific Analyses for Util as Planned,Due to Delays Encountered in Completing Sensitivity & Break Spectrum Analysis.Meeting Between NRC & Util Representatives Arranged for 8908101989-08-0101 August 1989 Informs of Inability to Submit plant-specific Analyses for Util as Planned,Due to Delays Encountered in Completing Sensitivity & Break Spectrum Analysis.Meeting Between NRC & Util Representatives Arranged for 890810 A07974, Advises That No Agreements Restricting Employees to Inform NRC of Potential Safety Issues Exist,Per V Stello1989-07-31031 July 1989 Advises That No Agreements Restricting Employees to Inform NRC of Potential Safety Issues Exist,Per V Stello ML20248B7931989-07-31031 July 1989 Forwards Response to NRC Request for Addl Info Re Util 890421 Application for Amend to License DPR-61,revising Tech Spec 3.6, Eccs. Revised Tech Spec Also Encl B13307, Responds to Generic Ltr 89-06, Task Action Plan Item I.D.2 - SPDS - 10CFR50.54(f). SPDS for Plants Meet Applicable Requirements of Suppl 1 to NUREG-0737 & Consistent W/ Majority of Positions Provided in NUREG-13421989-07-21021 July 1989 Responds to Generic Ltr 89-06, Task Action Plan Item I.D.2 - SPDS - 10CFR50.54(f). SPDS for Plants Meet Applicable Requirements of Suppl 1 to NUREG-0737 & Consistent W/ Majority of Positions Provided in NUREG-1342 A08037, Responds to Generic Ltr 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning. Plants Have Programs & Procedures in Place to Monitor Erosion/Corrosion for Both single-phase & two-phase Flow Sys1989-07-13013 July 1989 Responds to Generic Ltr 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning. Plants Have Programs & Procedures in Place to Monitor Erosion/Corrosion for Both single-phase & two-phase Flow Sys A08007, Requests Extension of Deadline for Response to Generic Ltr 89-06, Task Action Plan Item I.D.2-SPDS-10CFR50.54(f), to No Later than 890721.Addl Time Needed to Allow for Completion of Thorough Internal Review of Response1989-07-12012 July 1989 Requests Extension of Deadline for Response to Generic Ltr 89-06, Task Action Plan Item I.D.2-SPDS-10CFR50.54(f), to No Later than 890721.Addl Time Needed to Allow for Completion of Thorough Internal Review of Response B13282, Forwards Response to 890501 Request for Addl Info Re Util Const of New Switchgear Bldg at Plant1989-07-10010 July 1989 Forwards Response to 890501 Request for Addl Info Re Util Const of New Switchgear Bldg at Plant A08093, Advises That Fourth Quarterly Installment of 1989 Annual Fees Will Be Wire Transferred on 890731 in Payment of Invoices H1146,H1222,H1190 & H1151,per 10CFR1711989-07-0707 July 1989 Advises That Fourth Quarterly Installment of 1989 Annual Fees Will Be Wire Transferred on 890731 in Payment of Invoices H1146,H1222,H1190 & H1151,per 10CFR171 A08111, Advises That Payment for 10CFR170 Fee Sent to Jm Rodriquez Re NRC Review of Rev 11 to QA Topical Rept1989-07-0707 July 1989 Advises That Payment for 10CFR170 Fee Sent to Jm Rodriquez Re NRC Review of Rev 11 to QA Topical Rept A07951, Responds to Suppl 3 to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs. Issue Represents No Problem at Any Millstone Unit.Haddam Neck Valves Will Be Inspected for Leakage During Upcoming Refueling Outage1989-06-30030 June 1989 Responds to Suppl 3 to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs. Issue Represents No Problem at Any Millstone Unit.Haddam Neck Valves Will Be Inspected for Leakage During Upcoming Refueling Outage B13268, Submits Addl Info Re 890425 Proposed Rev to Tech Specs Administrative Controls Section Concerning High Radiation Areas,Per NRC 890505 Conference Call1989-06-26026 June 1989 Submits Addl Info Re 890425 Proposed Rev to Tech Specs Administrative Controls Section Concerning High Radiation Areas,Per NRC 890505 Conference Call B13215, Advises That One Technically Qualified & Trained Individual Per Site Will Man Health Physics Network & Emergency Notification Sys Telephone Lines at Plants,Per NRC Ltrs1989-06-23023 June 1989 Advises That One Technically Qualified & Trained Individual Per Site Will Man Health Physics Network & Emergency Notification Sys Telephone Lines at Plants,Per NRC Ltrs 1990-08-30
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CONNECTICUT YANKEE ATOMIC POWER COMPANY B E R L I N, CONNECTICUT P O. BOX 270 HARTFORD. CONNECTICUT 06141-0270 TELEPHONE 203-66s-5000 November 6,1985 Docket No. 50-213 A04547 Dr. Thomas E. Murley Regional Administrator, Region I ,
U. S. Nuclear Regulatory Commission 631 Park Avenue
' King of Prussia, PA 19406 Gentlemen:
Haddam Neck Plant Response to December 13,1984 Order Modifying License The purpose of this letter is to provide Connecticut Yankee Atomic Power Company's (CYAPCO) response to Section IV.C of the Order modifying the operating license which was issued on December 13,1984(l)
Background
On December 13, 1984, the NRC Staff issued a Notice of Violation and Proposed imposition of Civil Penalty and Order Modifying License to CYAPCO. These actions were a result of inspections conducted concerning the circumstances associated with the failure of the reactor cavity seal at the Haddam Neck Plant on August 21,1984.
Subsequent to the issuance of the subject Notice of Violation (NOV) and Order Modifying License, the Staff granted an extension to January 28, 1985 for responding to the Order Modifying License.(2) By letter dated January 7, 1983,(3) CYAPCO confirmed with the Staff our mutual understanding that the extension for responding to January 28, 1985 applied not only to the Order Modifying Licerise but also to the Notice of Violation.
l (1) 3. M. Taylor letter to W. G. Counsil, dated December 13,1984, Order Modifying License and Notice of Violation and Proposed Imposition of Civil Penalty, Docket No. 50-213, EA-84-il5.
(2) 3. M. Taylor letter to W. G. Counsil, dated December 26,1984.
(3) W. G. Counsil letter to J. M. Taylor , dated January 7,1985.
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[., w:[ 'By letter dated January 28,'1985,(4) CYAPCO responded to the subject Notice of Violation and the Order Modifying License. The response to the order outlined a 1 comprehensive plan to review design changes and the design change process.-
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utilized at;Haddam= Neck."The letter also included a description of other on-L going initiatives' within the' Northeast Utilities /CYAPCO organization .that are -
W related to our.overall plan for improving:the design change and safety' review process.
$ By letter dated Feliruary)6,1983(5), CYAPCO transmitted the resumes of the
- Plant Design Change Task Group members. : This completed our response to the Order.
im
- By1 1etter ' dated . March 22,.1985(6), CYAPCO described the interim corrective Lactionsson the design change : control process which were implemented '1n
- February 1985.
, By' letter dated April 23,1985,(7) the NRC Region 1 Administrator accepted the L program plan, the qualifications of the Task Group members and. the interim
' corrective actions.-
ByLletters dated April: l'l(8) and June 21,(9) 1985, the Plant L Design Change -
External Review Group provided the Regional Administrator.with status reports : '
l> : discussing the progress of their review and the schedule of activities.
- Final Report
'In accordance with Section.IV.B of the Order, the Plant Design Change Extern 31 o -Review Group-transmitted the Group's Final Report on September '6,1985(1W. ,
Of : the: 355 JPlant.. Design Change Requests L(PDCR) and 20,294 Work Permits / Orders reviewed during the period in question only one PDCR raised an L "(4) .W. G. Counsil-fetter to 3. M.. Taylor and Dr. T. E. Murley, dated January 28,1985.- g (5) W. G. Counsit letter to Dr. T. E. Murley, dated February 6,1985.
L '
- , (6). W. G. Counsit letter to Dr. T. E. Murley, dated March 22,1985.
- +
, (7) T. E. Murley letter to 3. F. Opeka, dated April 23,1985.
(8) D. E. Vandenburgh letter to Dr. T. E. Murley, dated ~ April 11, 1985.-
(9) D. E. Vandenburgh letter to Dr. T. E. Murley, dated June 21, 1985.
(10) D. E. Vandenburgh letter to Dr. T. E. Murley, dated September 6,1985.
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immediate safgty) concern. : The NRC was'promptly notified and License Event Report '85-017 .1 1
was 1: submitted < by : CYAPCO. Justification for continued operation' was provided and long term corrective actions will be supplied by
~
November 12, 1985 in a follow-up report. ' Detailed listings of other deficiencies
~
- m. ~ were ldentified in the' Connecticut. Yankee Plant Design Change Ta.4 Group
~
V,CYPDCTG) Final Report which accompanied the External Review Group's Final i: Report. - 1 Report Conclusions 1 '
s in general,.the(CYPD' CTG final report concluded that throughout the period _ of
- review, design changes have been made with conarn for both quality and safety.
~
In several instances, the ' identified deficiency was not 'related to the change itself, but to the original design basis of the system being modified.
The most frequent source of identified deficiencies was the seismic qualification of equipment.. The most signficant deficiencies identified in the CYPDCTG final report are: a) incomplete consideration of charging system outleakage in post-e accident release analyses and Technical Specifications, b) inconsistent seismic jqualification of the service-water system and portions of CVCS; c) potential
= degradation of containment isolation under certain post-accident conditions, and ,
d); inability' ofithe' plant 'to achieve ~ cold shutdown utilizing only seismically
- qualified equipment. ;
L Also, the CYPDCTG concluded that existing procedural controls over the design.
- change process' are effective. Only a.few deficiencies that occurred In past :
Edesign changes have not been addressed adequately in current' design change
~
i procedures. - A significant improvement in PDCR packages with' time was noted.- '
? Report Recommendations .
The CYPDCTG recommendations for improvements in the design change process .
were primarily.in the areas ~of:
' l. - Control of design basis information. ;
2.- _ Training of engineers ~on the design change process, ,
3.. The definition of Plant Design Change",
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- 4. - The documentation of activities that may not be controlled under PDCR's.. 4 u
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The need for a more integrated review process.. ,
6.- - Specific procedure improvements for clarity and consistency.
The CYPDCTG findings and recommendations were summarized in Tables 5,6,7 and 8 of the CYPDCTG Final Report.
i
~(11); R. H. Graves. letter to NRC-Document Control Desk, dated August 14, 1985.,
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Limprovement Plans
- A plan ~ for improvements based on evaluation of the .CYPDCTG findings _and v . recommendations is provided as - Attachment 1. The plan / includes (1) action
-items to be performed and (2) a schedule for completion of each specific action sitem which has. not Jalready been completed.~ To date,' the. completed action
~
. ' items have adopted the recommendations of the final report.
Special Reports .
1 .. . . , .
During the course of this review,:two additional design change problems were. ,
s ^ identified to.the CYPDCTG for consideration.(12) One of these design changes-
- ~'
- affected the Haddam Neck Piant, and the other' design change concerned . ,
Millstone Unit No.' 2. The CYPDCTG completed-its review of ~ these two plant
~
~ design changes and provided the following reports to the NRC by . letter dated October ll, 1985(13):
o "Special Report - Connecticut Yankee PDCR 713," dated August 30,1985
, : PDCR 713 involved modifications to the computer room and associated
.' smoke detectors.
o "Special Report - Millstone Unit 2 PDCR 2-8-85," dated September !!,
1985 PDCR 2-8-85 involved modifications to the pressurizer pressure control.
system.
The recommendations of these special reports are summarized in Attachment 2. --
J A plan for improvements 1 based on. evaluation of the CYPDCTG fin' dings .and rscommendations is included in Attachment'2 and will be included in the plan to
~ address the CYPDCTG findings and recommendations discussed in Attachment'l..
Summary in. summary,' the plans described in Attachments -1 and 2 provide our response to Section IV.C of the Order. The results of the planned evaluations 'and reviews
- discussed in Attachments 1 and 2 will be' documented, filed and available for n . f uture ~ review, CYAPCO hereby requests the NRC' review and approve the -
. attached plans in accordance with the Order.
t
'(12)l E. C. Wenzinger letter to R.'3. Schmidt, dated July 19,1985 (Docket No.
50-213),'and E. C. Wenzinger letter to R. 3. Schmidt, dated August 14, 1985 (Docket No. 50-336).
(13) 3. F. Opeka letter to E. C. Wenzinge.', dated October 11,1985.
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- If you have any questions or comments, please let me know.
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY GEOnu J. F. Opeka Senior Vice President By: -E. J//Mroczkap Vice Prdident Attachments
- - STATE OF CONNECTICUT )
) ss. Berlin COUNTY OF HARTFORD )
Then personally appeared before me E. J. Mroczka, who being duly sworn, did state that he is a Vice President of Connecticut Yankee Atomic Power Company, Licensee .herein, that he is authorized to execute and file the foregoing information in' the name and on behalf of the Licensee herein and that the statements contained in said information are true and correct to the best of his knowledge and belief.
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.. ,,i Docket No. 50-213 Attachment I Connecticut Yankee Improvement Plan a
November,1985
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g ;,3 : Deficiencies in Specific Plant Design Changes TABLE 5 Deficiency No; li - PDCR No. 294 RHR Purification Flow Valve Reach Rod !
Piping _is not'se.smically qualified.
Response
.The piping around valve RH-V-874A will be analyzed. The seismic qualif'ication i 'of the RHR. system has previously been identified as Issue 1.04 in the Integrated Safety ' Assessment Program. The analysis and schedule for modifications (if
. required) will be completed by January 31,1987.
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Deficiency No. 2: PDCR Nd.~ 306 Containment' Fan Filter Timers
- No procedure to ensure continued paper functioning of the timers.
' [ Response: f A surveillance procedure will be established by January 15,1986.
- Deficiency No. 3: -PDCR 326 Fire Suppression System .
- Seismic evaluation of fire ' suppression system located above safety related ;
equipment. -
Response
The fire suppression piping which is located abo.ve safety related equipment will bej seismically analyzed. The analysis?and schedule for modifications -(if required) will be completed by July 30,1986.
, ' Deficiency No. 4: PDCR 326 Fire Suppression System Impact of fire suppression fluids sprayed on safety related equipment.
R_eponse:
In ' 1983, the Nuclear Regulatory Commission issued an I&E Information Notice
-(83-41) entitled "Acutation of Fire Suppression Systems Causing Inoperability of Safety-Related Equipment". This notice highlighted several examples where actuation of fire suppression systems' caused damage or inoperability to systems
~'
important to safety. Based on this concern, NU initiated an evaluation for the three operating plants to determine if any fire suppression system could cause damage or incapacitate shutdown systems.
The evaluation was comprehensive and involved verification walkdowns, drawing reviews, verification of fire system designs, installation and operating characteristics,' plant procedures and a final determination of its impact on safe
- shutdown systems. - The report for- CYAPCO concluded that operation and/or failure of fire suppression systems had no impact on safe shutdown capability.
- . One' exception was noted and corrective action in terms of a hardware L
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modification is scheduled to be implemented during the January 1986 refueling outage. The report is entitled " Inadvertent Operation / Rupture of Fire Protection Equipment" dated January 1984, and a copy is available for your review.
This deficiency is resolved.
Deficiency No. 5: PDCR 333 Combustible Gas Detection System No procedures to establish maintenance and calibration of the system.
Response
Maintenance Further detailsand calibration on this procedures deficiency will be were provided in established by July 2,19(8Q.
our August 30,1985 letter.11 Deficiency No._6: PDCR 344 - Containment Isolation Reset Modification inadequate training plan and procedures to adequately identify all steps to clear SI/HCP bluck. ,
Response
Procedures and training plans will be upgraded by May 2,1986.
Deficiency No. 7: PDCR 347 Reactor Coolant System Venting System Uncertainty of ability of valves to function with water.
Response
The reactor vessel and pressurizer non-condensible gas vent system isolation valve design will be evaluated to determine the effects of passing water flow.
The evaluation will be completed by February 28, 1986 and a schedule of modifications (if any) will then be determined.
Deficiency No. 8: PDCR 347 Reactor Coolant System Venting System Failure to test valves against full differential pressure.
Response: ,
The reactor vessel and pressurizer non-condensible gas vent system isolation valves will be evaluated to confirm the ability to open and close against full differential pressure. The evaluaticn will be completed by February 28, 1986.
(1) J. F. Opeka letter to Dr. T. E. Murley, dated August 30, 1985.
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! D'eficiency No. 9:1 PDCR 347 Reactor Coolant System Venting System Failure of AOP 3.2-22 to utilize revised calculations on venting times.
, c
. Responses AOP 3.2-22 will be revised by July 2,1986.
- Deficiency No.10: PDCR 347 Reactor Coolant System Venting System L
Failure to verify actual plug movement in surveillance tests.--
r.
Responses' -
- Surveillance procedures will be revised by July 2,1986.
Deficiency No.113 PDCR 368 RCP. Seal Water Supply Valves (Uncertainty of seismic qualification of the RCP seal water system. >
. Response -
The requirement for RCP operation in post accident conditions will be verif_ led '
'and the seal water piping system will be seismically analyzed. Analysis and
. modifications' (if required) will be combined with evaluations regarding PDCR 380 whenever possible. The analysis will be completed by January 31, 1987..
i<
Deficiency No.12: PDCR 317.TMI 2.1.8 Additional Equipment to Follow Course -
c Accidents -
- Inconsistent procedures as related to calculations.
ac
" Response:
l-Procedures will be clarified by May 2,1986.
.~, Deficiency No.13: PDCR 380 - RCP Component Cooling Water and Seal Water -
- ,.,.. isolation Modification.
Inadequate ' dose analysis and Tech. Spec. treatment of charging system outleakage. ,
Ret.wnse CYAPCO has implemented necessary administrative controls to monitor and limit the combined leakage from -the RHR and charging systems to less ti.an
. three liters per hour. This will ensure that the actual leakage from all sources is
! ' within that assumed in the radiological analysis. Additionally, CYAPCO wl!!
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submit a liunse amendment request to formalize the above mentioned administrative measures by January 313 1986. This deficiency was discussed in LER 85-17 submitted August 14, 1985.(21 Deficiency No.14: PDCR 380 - RCP Component Cooling Water and Seal Water Isolation Modification Unevaluated impact of modification as related to reduced containment integrity.
. Response:
The requirement for RCP operation in post accident conditions will be verified and the CCW and seal injection systems pip;ng analyzed accordingly. The analysis will be combined with PDCR 368. Modifications (if any) will be
' identified and a schedule for implementation will be developed by January 31, 1986
-Deficiency 15: PDCR 380 - RCP Component Cooling Water and Seal Water Isolation Modification Inadequate precedures to assure prompt manual valve closure.
Response
Procedures will be upgraded by May 2,1986.
Deficiency No.16: PDCR 380 - RCP Component Cooling Water and Seal Water injection Modification.
Seismic qualification of isolation valves and associated piping.
Response
See response to Deficiency No.11.
Deficiency No.1,7_: PDCR 380 - RCP Component Conting Water and Seal Water Injection Modification.
Faulty logic for activation of valve FCV-608.
Response
The control logic for the CCW return ficw control valve will be reviewed to determine if a high flow signal will keep tl e vaive closed. Modifications (if any) will be identified and a schedule for in.p!ementation will be completed by March 28,1986.
(2) R. H. Graves letter to NRC Document Control Desk dated August 14,1985, transmitting LER 50-213/85-017-00 entitled " Post-LOCA Release Paths Outside Containment."
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Deficiency No.18: PDCR 380 - RCP Component Cooling Water and Seal Water
- Isolation Modification. ,
Potential release path from contanment via seal return line'and relief valve CH-RV-332.1
Response
See' response to Deficiency No.13.
{
Deficiency No.' 192 PDCR 380 - RCP Component Cooling Water and Seal Water
- Isolation Modification Resolution of CYPDCTG Report " Containment Piping Penetrations" Responses
- The current configuration of each containment penetration will be reviewed to determine compliance to isolation criteria. . Deficiencies 11,16 and '18 will be i included. The analysis and identification of modifications (if any) and exemption requests will be completed by July 30,1986.
Deficiency No. 20: PDCR Nos. 384/401 - Automatic Initiation of Auxiliary
- , Feedwater
. - -- Questionable design basis analysis of the AFW system.
- Response:
a.
The AFW system design basis will be evaluated in more detail.- It is noted that our letter dated Septepber 20, 1985 provides considerable detail on the current J AFW- system design.(3/ This evaluation will be completed and modifications (if any) will be identified by August 31,1986.
Deficiency No. 21:- PDCR 388 - Primary Vent Stack Ring Evaluate the means of accomplishing cold reactor shutdown following a seismic event utilizing only seismically qualified and protected equipment.
- Response:
~
- CYAPCO will . evaluate the need' to achieve cold shutdown in light of design Lbasis, SEP, accident analyses, and current operating procedures by July 30, 1986 and identify modifications..(if ;any) required in _ the evaluation.-. Responses to
- ' Deficiency defined in .25 the &; 36 will 19, January be included in th9.)~will 1981 letterW evaluation. The Staffduring be- considered position as this
^
~ evaluation.
~(3) . 3. F. Opeka letter to 3. A. Zwolinski, dated September 20,1985.
1 [(4) - D. G.' Eisenhut letter to All Licensees of Operating Plants and Applicants for Operating Licenses and Holders of Construction Permits, dated January 19, 1981, entitled "Information Regarding the Program For Environmental.
. Qualification of Safety-Related Electrical Equipment (Generic Letter 81-
- 05).~
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( Deficiency No. 22: PDCR 418 - PORY and Block Valve Logic Modification
, Failure to seismically qualify relays and mounting. ,
- Response:
The seismic qualification of th"e PORV and Block valve relays and their mounting .
on the Main Control Board will.be evaluated and modifications Of any) will be identified by July 30,1986.
Deficiency No. 23: PDCR 436~ Upgrade of. Spent Fuel Building North Crane
=
CRS-1A Upgrade bothf fuel. handling : cranes equipment and QA classifications and refueling manipulation to QA Category I.
Response: -
The need to upgrade the cranes to QA Category 1 (safety related) will be n evaluated and modifications Qf any) will be identified by August 31,'1986.;
Deficiency No. 24:- PDCP .443 - Flood Protection Requirements Failure to test or verify adequacy of cooling of service water pumps with flood' protective covers in place. '
' Response: -
~
Inservice testing or heat load calculations will be performed by July 2,1986.
- Deficiency No. 25: PDCR 459 Re-evaluation of Safety Related Piping
.Re-evaluate scope of pre,'ect to ensure safe reactor thutdown to cold conditions following a seismic event.
~ '
- Reshnse:
9 See response to Deficiency No. 21
- Deficiency No. 26: PDCR 486 Terry Turbine Steam Control.-
Ina'dequate consideration of operabilty with loss'of control air.
Response
Automatic initiation with loss of control air may cause the turbines to overspeed ~
, ~ and result in a turbine trip and loss of auxiliary feedwater. The scenario will be canalyzed and modifications Of any) will be identified by March 28,1986. !
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- Deficiency No. 27: .PDCR 486 Terry Turbine Steam Control Incomplete consideration of error analysis' in verifying the capacity ,of the
. system.
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^ Response:
System capacity. testing will be performed by July 2,1986.
- Deficiency No. 28: ~ PDCR 592 Charging Pump Failure to assess impact of change of pump curve on DBA.- -
Response
~
The evaluatlon of the effect of the change in pump performance on the small-break LOCA analysis will be completed by April 30,1986. The evaluation of the effect of the change in pump performance on the feed and bleed analysis will be completed by January 31,1986.
Deficiency No. 29: PDCR No. 392 Charging Pump Failure to assess degraded voltage operability of main lube oil motor.
< Response: ,
' Degraded voltage conditions will be' evaluated and modifications (if any) will be identified by January 31,1986.
L ~
g Deficiency No. 30: PDCR 592 Charging Pump Failure to upgrade several procedures.
Response
, Procedures will be upgraded by July 2,1986.
. Deficiency No. 31: PDCR 626 Replacement of Foxboro Feedwater Flow i Transmitters Failure to establish the uncertainty of flow measurement.
Response
~ Flow measurment uncertainty will be established.and included in surveillance
- y. procedures and accident analyses by May 1,1986.
. Deficiency No. 32: PDCR No. 626 Replacement 'of Foxboro Feedwater Flow i' Transmitters
[ - Failure to determine seismic adequacy of the Hagen flow transmitters.
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Response
The seismic . adequacy of the Hagen flow transmitters, which supply a reactor trip function, and associated sensing lines will be determined.. The analysis will-be completed and modifications (if any) will be identified by July 30,1986.
Deficiency No. 33: PDCR 634 Replacement of Foxboro Pressure Transmitters PT 403 & 404' Failure to seismically qualify instrument tubing.
Response: .
Instrument tubing will be analyzed'for seismic capability by August 31,1986 and modifications needed (if any) will be identified.
Deficiency No. 34: PDCR 634 Replacernent of Foxboro Pressure Transmitters-PT403 and PT404.
I
~ Failure to clarify Reg. Guide 1.97. submittal.
Response
~ The Reg.. Guide 'l.97 report for Connecticut Yankee was submitted on May 31, 1984. This submittal.will be revised by September 30,1986 if the analysis results of Deficiency ' No. 33 ' determine the instruments are not fully seismically qualified.
]. c Deficiency No. 35: PDCR 653 Vital Inverter Cabinet Ventilation Failure to. conduct seismic analysis . on cabinets with --l actual components locations.
^
' Response:
. Seismic analyses using actual component locations'will be completed by February 28,1986 and will identify any needed modifications.
Deficiency No. 36: . PDCR 660 Relief Valve for Spent Fuel Pool Heat Exchanger Failure to perform complete seismic analysis of service water system.
' Response:
See response to Deficiency No. 21.-- ,
+ ' Deficiency No. 37:.. PDCR 684 Replacement of RCS Loop RTDS Incomplete review of acceptance limits for the RTD's.
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-9 Response: .
'A sensitivity study will be performed to determine if the. acceptance band for-the RTD's is appropriate for all power levels, and to determine its acceptability considering three loop operation, and the most limiting desiga basis event. The study and identification of modifications (if any) will be completed by August 31,-.
1986. <
Deficiency No. 38: . PDCR 684 Replacement of RCS Loop RTD's -
Failure to conduct response t'irie tests.
- Response:
Response time testing will be conducted on RTD's installed during the 1986 refueling outage as soon as practical following the 1986 outage. The actual date for performing the test will be governed by the duration of the outage.
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Design' Change Process Recommendations Table 6 F R.ecommendation 1:
Expand scope of controlled documen+ation~ to include design bases, classifications, and other information. -
-Respense:
The updated FSAR fora Connecticut Yankee will ' include controlled documentation for the design bases, classifications, system descriptions and other information. The updated FSAR wi)1 accordance with our October 11,1985 letter.ll) be completed and submitted in Recommendation 2:
Improve timeliness and quality of "as built" documentation updating.
Response
A plan to address this recommendation will be developed by February 28,-1986.
Recommendatien 3:
Provide training on the plant modification process.
4
Response
- 1. : Familiarization of PDCR requirements, design inputs, safety evaluations, and all associated PDCR NEO procedures will be stressed in the NEO Procedure Familiarization Course starting November 30,1985. 4
.2. Detailed PDCR training will be conducted by supervisors in departmental--
sessions. Students will be instructed in how their department is to perform the specific steps necessary to implement the PDCR and associated procedures. Training will be completed by July 31,1986.
Recommendation 4:
Revise NEO3.03, " Preparation, Review, and Disposition of Plant Design Change
-Requests", to address PDCRs of general scope and PDCRs not completed.
Response
$ - NEO3.03 will be revised and issued by March 15,1986.
~
(1) 3. F. Opeka letter to H. L. Thompson,-3r.,' dated October 11, 1985.
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Recommendation 5:
Expedite'.':the -Implementation of NEOS.04, " Safety Evaluation . of - Proposed
. Changes to Station Procedures"
Response
NEO 8.04 will be issued by January 31,1986.
Recommendation 6:
- Evaluate the effectiveness of the QA program to ensure compliance with process procedures.
Response
An engineering assurance program will be developed and implemented as -a--
~ NUSCO _QA function by April 1,- 1986.
-Recommendation 7:
' Develop a more effective definition of " plant design change".
~ Response:
A . Task Force will be appointed to develop and review this and other related' ~
issues.-- NEO 3.03 will be revised and reissued by November 30,1986.
Recommendation 8:
Perform a technical review of specified categories of Automated Work Orders.
- Response:
' See response to Recommendation 7.
-Recommendation 9:
~
( . Develop a simplified means to document plant design changes that are " remote to safety" or " equivalent component".
. Response:
See response to Recommendation 7.
Recommendation '10:
- Attempt to streamline PDCR process.
Response
See' response to Recommendation 7.
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2 Recomendation l'l :
Revise NE03.03 to prohibit unrelated changes on a single PDCR.
Response
[ iSee response to Recommendation 4.
Recommendation 12: .
. Provide improved multi-discipline reviews and integration.
Response
.. A' plan to address this recommendation' will,be developed by-February 28, 1986,
~
' with the intent of completing implementation of the plan by December 31,-1986.
Recommendation 13:
' Provide _ guidance / training- on the -interface needs/ reviews on technical -
documents.
Response
- A D new NE&O ' proce' dure on " Interface Controls" will' . be developed
- and -
~
implemented by April 1,1986. . This procedure will provide-the mechanism for-the -guidance / training .to satisfy this recommendation. -.This procedure will also
. provide the mechanisni ta delete the interface control : requirements now
- 4
'specified in the project assignment procedure.
- Recommendation 14:-
Improve' incorporation of system interaction criteria and secondary effects in
! design changes. -
U Response -
i: . .
See response to Recommendation 12.
Recommendation 15
~
Develop controlled documentation for the impact of location dependent issues
' (e.g., seismic, fire protection, flooding, EEQ).
Response
A plan to address this recommendation will be developed by February 28,1986.
Recommendation 16: - -
^3 (Develop means to evaluate the cumulative effects of a number of minor changes (e.g., core boring, control board additions). -
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Response
-See response to Recommendation 12.
j Recom'mendation 17i Develop an NEO level procedure on project descriptions, perhaps elevating GEC
- Procedure 2.07.
- Response: -
.; A .new NE&O_ ' procedure on " Project Descriptions" will be developed and
-implemented by April 1,1986.
L-Recommendation 18:
- Address the recommendations in Table 7 on specific procedure changes.
Response:-:
Refer to'the following recommendations for Table 7 and their responses.
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Table 7
' Recommendation l':- Procedure 5.05
- 1. - Design verification can be performed using independent review, alternate calculation- or -testing. This proced.ure should be revised to . require a decision and indication of the method of design verification.
2.1 iSome items do not seem appropriate for the checklist, Figure 7.1.
~
For example,31, and 32 appear to address ~ questions. raised after the document
. . review has been completed. . Review each item 'on the list for
- appropriateness and revise as necessary.
,p 3. . Clarify' the . application of the design input documentation requirements.
~ For example, refer to NEO 5.05 in' step 6.2.3.4 of NEO 3.03.
Response
. NEO Procedure '5.05 will be revised to address the above recommendations and i
. th: revised procedure will be ssued by February 1,1986.
~ Recommendation 24 Procedure 3.03 :
= 1.- Clarify- the application of the_ design. input ' documentation requirements. ,
, For example, refer to NEO 5.05 in step 6.2.3.4 of NEO 3.03. ,
'2. Step 6.2.2.2 of 7.02 specifies walkdown criteria be determined in the PDCR.. However, this is not specified in NEO 3.03. Revise either 7.02 or '
~ 3.03 to be consistent.
4 s
Response
" NEO Procedure' 3.03 will be. revised to address the above recommendations and ,
1 the revised procedure will be issued by March 15,1986.
- Recommendation 3: ' Procedure NEO 5.11 Add documentation indicating whether or not there is an impact on the safety or O environment :eviews on Figure 7.2.'
< Response:
- No action necessary. This recommendation has been implemented.
R'ecommendation 4: Procedure NEO.5.15 Develop and release in a timely manner.
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- Response:'
.No action necessary.' This recommendation has been implemented.
- Recommendation 5
- . Procedure NEO 7.01 -
r 1.. Resolve - conflict between parallel review specified in step 6.16 and sequential review shown.in the flow chart for OUES and QC.
- 2. Reword step 6.2.4 to _ clarify the timing of inspection. requirements. The wording implies .that inspection is completed prior to approval of work -
- order..
m 3. - Define Unit Engineer as indicated in step 6.4
' _ 4. - ' Step 6.16 is performed by the Job Supervisor-while the flow chart shows
. that it is performed by the originator. Resolve this conflict.
7- 5.. - Add requirement for the appropriate QC group and the Design group to be
' responsible for verification of."As Builts". -
'6. Resolve conflicting definition of when turnover occurs.
Response
~
NEO Procedure 7'.01 will be revised to address the above recommendations and
.t.he revised procedures will be issued by February-1,1986.
Recommendation 6: Procedure NEO 7.02
- 11. . Define.the requirements for a pre-construction meeting that-is'shown in
- the flow chart.
2.' ! Step 6.2.2.2 of--7.02 ' specifies walkdown criteria be determined in' the ~
PDCR.= However, this is not specified in NEO 3.03. Revise either 7.02 or -
, 3.03 to be consistent.
< -3. ' Resolve corsilicting definition of when turnover occurs.
Response
NEO Procedure.7,02 will be revised to address the above recommendation and
- , the revised procedure will be issued by April 1,1986.
Recommendation 7:- ~ Procedure NEO 7.03
- 1. -- ~ Revise to include review and approval of test procedures. ,
' 2.' , Revise Das necessary to include NUSCO managers / supervisors in the
' Instruction Section to reflect the Responsibility Section.
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- 3. ' Clarify the definitions for Retest,. Pre-Operation Test, Phase I Test and Phase 11 Test to indicate the distinction between the terms.
- 4. Reorder as necessary the substeps in Step 6.3.~
- 5. . Clarify the term "ultin ate acceptance".
- 6.- 3 Resolve conflicting definition of when turnover occurs.
Respo'nse:
. NEO Procedurel7.03 will be revised to address the above recommendations and
- the revised procedure will be issued by April 1,1986.
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PART I- WORK PERMITS / ORDERS' INVOLVING DESIGN CHANGES OF POTENTIAL SAFETY SIGNIFICANCE TABLE 8 Open Items Work Permit -
Number Description of Change Required Evaluation flC0429 Relocated charging pump discharge Seismic Evaluation pressure gauge MA0051: Installed 1/2" drain valve on Seismic Evaluation seal water relief valve return piping M A 0821_' Changed m'anual steam generator- Seismic Evaluation blowdown valve to another model MA0831 L Installed non-seismic monitor Seismic Evaluations or stand near seismic equipment remove monitor stand MA1102 Installed small tank'in Safety- Seismic Evaluation Injection Cubicle
. MA4604 Change'd manual reactor vessel Seismic Evaluation -
vent valve to heavier model -
L CY840104 Changed steam generator level Seismic Evaluation Isolation valve to another model LCY8404526 Replaced HPSI recirc. line pressure Evaluate consequences
, gauge with higher range gauge CY8406242 - ' Seal welded a plug on RHR relief Verify that post valve - No post weld heat weld heat treatment treatment is not required.
. Response:
The required evaluations will be completed by June 30,1986 except for Work Permit Number CY8406242 which will be completed by February 28,1986.
4
(.
- q, . -g 18 PART ll- WORK PERMITS / ORDERS INVOLVING POTENTIAL DESIGN CHANGES TABLE 8
. Open Items
-Work Permit Number Description of Worl< Permit / Order Action MA0693 ' These 6 WP's involved plugging Inspect Heat Exchangers MA2174 of Emergency Diesel Generator to determine total MA2176 Heat Exchange Tubes - Total number of tubes plugged MA2424 number of plugged tubes could and if design basis is MA2822 not be determined invalidated.
MA2851 IC0080 Hook up RTD on Polar Crane - Containment entry required to evaluate-IC0203 Relocated gauges on service work performed, water to CAR fan pressure Shutdown Required sensing lines IC0444 Installe'd sirens in Containment
' M A0065 Installed gates on S. G. skirts MA0136 Modified grating and ladders near RCP's MA0220 Welded unistrut to polar crane MA1189 Cable modifications to CAR fan MA1485 Installed light changing fixture on polar crane MA1816 Elec. Change due to relocation of spray valve air compressors CY8405888 Installed handrails around steam generators CY8406326 ' Replace PORV air pressure gauge with different model.
CY8408165 Drill & tap holes in RCP's
~ CY8409197 Resupport SG vent line CY8400453 Replace pressurizer steam sample Not yet performed and CY8400454 isol. valves with different valves inside containment.
-- CY8400455 Review prior to work for PDCR requirement.
CY3409926 - Modify Rx Cavity Railing Not yet performed and inside containment.
Review for potential secondary effects.
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Response
The required evaluations and inspections will be completed by July 2,1986.
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, tj -- .. s .. y Part Ill'- PDCR Reviews Requiring Future Site Inspecton
_ Table 8 PDCR#' Title ~ Action
~
~
460 Head Area ' Cable Support Perform as-built review Structure (HACSS) .of HACSS/ Missile Shield to verify' seismic design requirements were met.
Requires shutdown.
. Response
< The review of PDCR460 will be completed by June 30,'1986.
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Docket No. 50-213 s
- Attachment 2 Connecticut Yankee Special Reports 9
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November,1985 s - _
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Recommendations of Special Report Connecticut Yankee PDCR 713
. Recommendation 1:
1 Revise ' Tech. ISpec. 3.2.2 to . clearly _ identify the applicable' detectors in the
. control room.J- As a minimum, assure that Standard Tech Specs are definitive in this regard.'
- Response:
W
? 'A license-amendment request to revise Technical Specification 3.2.2 will be
~
k-submitted- by June ' 1,' .1986.- The ! request will clearly identify the applicable
' detectors in the Control Room Fire Area.
Recommendation 2:
Provide improved controlled documentation to describe 'the plant design bases (Ref: CYPDCTG Final Report, Table 6, Recommendation 1).
Response
The' : updated FSAR for. Connecticut ~ Yankee will include contro!!ed
~
documentation- for the design bases, classifications, system descriptions _ and
' other : Information. The updated FSAR_ wi)1
- accordance with our October 11,1985 letter.LI) be completed 'and submitted in i Recommendation 3:
Increase .the ' awareness of' design engineers with respect to Tech. Specs. This
. action could be included in the training already recommended. (Ref: CYPDCTG -
Final Report, Table 6, Recommendation 3).-
Response
- 1. . Familiarization of PDCR requirements, design-_ inputs, safety. evaluations,-
and all associated PDCR NEO procedures will be stressed .in" the NEO
- < - Procedure Familiarization Course starting November 30,'_1985.
'2. Detailed PDCR training will be conducted by supervisors in departmental F
, ; sessions. Students will be instructed in how their department is to perform -
the specific steps necessary (to implement the . PDCR and associated procedures. Training will be completed by July 31,1986.
Recommendation 4:
Revise procedures as follows:
- a. In NEO 3.03, page 1 of Figure'7.1, change " Fire Protection" to Fire -
Protection QA" and "Radwaste System" to "Radwaste System QA".
- b. Add an item on the: Generation Fire Protection Engineering checklist to
- = address Tech. Specs.
L(1) 3. F. Opeka~ letter to H. L. Thompson, Jr., dated October 11,1985.
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fc. . Add an item on Fir;ure 7.1 of NEO 5.05 to address Tech. Specs.
- d. LRevise NEO 5.12Jt o. include GFPE: PDCR review check-off list.' . Revise H ~.NEO 5.05 to' permit use of GFPE check-off list during PDCR. verification
- ac'tivities.
~
]
~ Response: :
~
~
4.a - . NEO Procedure 3.03 will be revised and issued by March 15,1986.
4.b ' The item to address Technical Specifications has been added.
4.c,- . = NEO Procedure 5.05 will be revised and issued by_ February 1,1986.
14.d.':1). NEO Procedure 5.12 has been revised and issued.
'2) . - NEO Procedure' 3.05 will be revised and issued by April 1,1986.
Recommendation' 5:
, Revise SUR 5.5-13 to reflect all smoke detectors.
~
- Response:: -
' SUR 5.5-13 will be revised by January 31, 1986.
[: -Recommendation 6:
~
z 4 Assure that QA/NRB' audits of Tech. Specs verify the' adequacy of surveillance L procedures that implement Tech. Spec. requirements.
- Response:
~
M : The. adequacy of surveillance procedures is verified as part of the QA/NRB audit
" program. Improvements were made in this area,'in 1983 when the responsibility 1 for NRB audits of Tech. Spec. was assigned to the Quality Assurance Branch and w , teams-_ of "QA auditors" and " technical experts" were then utilized to- perform these audits.' The benefits of this change in direction have not yet been fully
"~
realized. ~ Therefore, a new program will be established by January _15,1986 to
- verify the adequacy of surveillance procedures.
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