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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 Amend Deletes Certain TSs Either No Longer Applicable to Permanently Shutdown & Defueled State of Reactor or Duplicate Regulatory Requirements CY-99-137, Notifies NRC of Intent to Apply Haddam Neck Plant 10CFR50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 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 05000213/LER-1996-030-02, Forwards LER 96-030-02 Submitted,Per 10CFR50.73.Attachment C to Rept Contains Confidential Info & as Such Was Included as Separate & Detachable Part of Original LER IAW 10CFR20.2203(b)(2)1999-08-13013 August 1999 Forwards LER 96-030-02 Submitted,Per 10CFR50.73.Attachment C to Rept Contains Confidential Info & as Such Was Included as Separate & Detachable Part of Original LER IAW 10CFR20.2203(b)(2) 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 IR 05000213/19980061999-06-0909 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 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 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 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 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 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 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 DD-99-01, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Directors Decision DD-99-01 Expired.Commission Declined Any Review.Decision Became Final Action on 990208.With Certificate of Svc.Served on 9902171999-02-16016 February 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Directors Decision DD-99-01 Expired.Commission Declined Any Review.Decision Became Final Action on 990208.With Certificate of Svc.Served on 990217 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 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 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 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 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 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 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 05000213/LER-1996-030-02, Forwards LER 96-030-02 Submitted,Per 10CFR50.73.Attachment C to Rept Contains Confidential Info & as Such Was Included as Separate & Detachable Part of Original LER IAW 10CFR20.2203(b)(2)1999-08-13013 August 1999 Forwards LER 96-030-02 Submitted,Per 10CFR50.73.Attachment C to Rept Contains Confidential Info & as Such Was Included as Separate & Detachable Part of Original LER IAW 10CFR20.2203(b)(2) 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 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 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-98-154, 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-98-062, 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-98-129, 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 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 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 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 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 B13625, Forwards Response to NRC Request for Addl Info Re 900825 Application for Amend to License DPR-61 Re ESFAS Instrumentation,As Agreed to During 900828 Discussion W/Nrc1990-08-29029 August 1990 Forwards Response to NRC Request for Addl Info Re 900825 Application for Amend to License DPR-61 Re ESFAS Instrumentation,As Agreed to During 900828 Discussion W/Nrc 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 A07335, 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 Found1990-07-0606 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 A08646, 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 Facility1990-07-0303 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 B13562, Forwards Vols 1-4 to Connecticut Yankee Simulator Certification Submittal..., Containing Info Re Generic Procedure Governing Certification of Plant Simulator & Performance Test Results,Per 10CFR55.45(b)(5)(ii)1990-07-0303 July 1990 Forwards Vols 1-4 to Connecticut Yankee Simulator Certification Submittal..., Containing Info Re Generic Procedure Governing Certification of Plant Simulator & Performance Test Results,Per 10CFR55.45(b)(5)(ii) ML20055D7191990-06-29029 June 1990 Amends 900604 Rev 13 to QA Program B13564, Provides NRC W/Info Re Plant Pressurizer as follow-up to 900607 Meeting.Info Particularly Concerns Disposition of Three Indications on Pressurizer Inner Surface & Discussion of Resolution of Previous Indication1990-06-29029 June 1990 Provides NRC W/Info Re Plant Pressurizer as follow-up to 900607 Meeting.Info Particularly Concerns Disposition of Three Indications on Pressurizer Inner Surface & Discussion of Resolution of Previous Indication B13554, Advises That Licensed Operator OP-10775 Will Not Be Reinstated to Licensed Duties & License Will Expire Due to Failure to Satisfy Medical Requirements of 10CFR55.211990-06-21021 June 1990 Advises That Licensed Operator OP-10775 Will Not Be Reinstated to Licensed Duties & License Will Expire Due to Failure to Satisfy Medical Requirements of 10CFR55.21 A08661, Forwards Electromagnetic Interference (EMI) Test Procedure ST 11.7-51, Reactor Protection Sys EMI Environ Test. Procedure Based on NUREG/CR-3270, Investigation of EMI Levels in Commercial Nuclear Power Plants1990-06-21021 June 1990 Forwards Electromagnetic Interference (EMI) Test Procedure ST 11.7-51, Reactor Protection Sys EMI Environ Test. Procedure Based on NUREG/CR-3270, Investigation of EMI Levels in Commercial Nuclear Power Plants B13548, Responds to & Comments on Findings of SALP Board W/Emphasis on Recommendations for Individual Evaluation Categories.Util Recognizes Importance of Striving to Improve & Will Continue to Pursue Positive Initiatives in Listed Areas1990-06-19019 June 1990 Responds to & Comments on Findings of SALP Board W/Emphasis on Recommendations for Individual Evaluation Categories.Util Recognizes Importance of Striving to Improve & Will Continue to Pursue Positive Initiatives in Listed Areas B13539, Forwards Comments on SER Re Fire Protection for New Switchgear Bldg.Comments Clarify & Revise Review to Reflect Actual Plant Comfigurations1990-06-11011 June 1990 Forwards Comments on SER Re Fire Protection for New Switchgear Bldg.Comments Clarify & Revise Review to Reflect Actual Plant Comfigurations B13541, Clarifies 900509 Application for Amend to License DPR-61 Re Use of Solid Type 304 Stainless Steel Filler Rods.Proposed Tech Specs Will Be Reworded to Limit Scope of Applicability to Two Type 304 Stainless Steel Filler Rods1990-06-0808 June 1990 Clarifies 900509 Application for Amend to License DPR-61 Re Use of Solid Type 304 Stainless Steel Filler Rods.Proposed Tech Specs Will Be Reworded to Limit Scope of Applicability to Two Type 304 Stainless Steel Filler Rods B13511, Forwards WCAP-12532, Review of Upper Shelf Charpy Energy Behavior of Matls in Haddam Neck Reactor Vessel. Rept Reviews Status of Core Region Matls Re Upper Shelf Fracture Toughness Issue,Per 10CFR50,App G1990-06-0606 June 1990 Forwards WCAP-12532, Review of Upper Shelf Charpy Energy Behavior of Matls in Haddam Neck Reactor Vessel. Rept Reviews Status of Core Region Matls Re Upper Shelf Fracture Toughness Issue,Per 10CFR50,App G B13530, Forwards Proposed Rev 13 to Northeast Utils QA Program Topical Rept1990-06-0404 June 1990 Forwards Proposed Rev 13 to Northeast Utils QA Program Topical Rept ML20043D5791990-06-0101 June 1990 Proposes Alternate Schedule for Completion of Item 4 of Generic Ltr 89-13.Revised Schedule Appropriate & Prudent & Will Ensure Complete & Accurate Response to Item 4 of Generic Ltr for Plants B13529, Forwards Bimonthly Progress Rept 22 Re New Switchgear Bldg Const,Per 860930 Commitment.All Const Work Complete Except Minor Punchlist Items1990-05-31031 May 1990 Forwards Bimonthly Progress Rept 22 Re New Switchgear Bldg Const,Per 860930 Commitment.All Const Work Complete Except Minor Punchlist Items B13527, Provides Updates to plant-specific Nuclear Training Manuals, Per Commitment.W/O Encls1990-05-15015 May 1990 Provides Updates to plant-specific Nuclear Training Manuals, Per Commitment.W/O Encls B13205, Forwards Nonproprietary WCAP-12552 & Proprietary WCAP-12590, Connecticut Yankee Thermal Shield Removal Licensing Rept1990-05-0909 May 1990 Forwards Nonproprietary WCAP-12552 & Proprietary WCAP-12590, Connecticut Yankee Thermal Shield Removal Licensing Rept B13506, Forwards Rev 21 to Security Plan.Rev Withheld (Ref 10CFR2.790(a))1990-05-0808 May 1990 Forwards Rev 21 to Security Plan.Rev Withheld (Ref 10CFR2.790(a)) B13362, Forwards List of Isap Topics,Update on Isap Topic Review, Evaluation of New or Reevaluation of Existing Isap Topics, Control Room Design Review & Human Engineering Discrepancies Summary,Integrated Implementation Schedule & Summary Table1990-04-30030 April 1990 Forwards List of Isap Topics,Update on Isap Topic Review, Evaluation of New or Reevaluation of Existing Isap Topics, Control Room Design Review & Human Engineering Discrepancies Summary,Integrated Implementation Schedule & Summary Table B13518, Forwards Rev to Distribution List for NRC Correspondence & Advises That EA Debarba Will Assume Position of Nuclear Station Director,Replacing DB Miller,Effective 9004281990-04-27027 April 1990 Forwards Rev to Distribution List for NRC Correspondence & Advises That EA Debarba Will Assume Position of Nuclear Station Director,Replacing DB Miller,Effective 900428 A08634, Advises of Receipt of Invoices 10660,10742 & 10665 for Payment of Annual Fee Per 10CFR171 for 19901990-04-10010 April 1990 Advises of Receipt of Invoices 10660,10742 & 10665 for Payment of Annual Fee Per 10CFR171 for 1990 ML20012F5481990-04-0505 April 1990 Forwards 1989 Annual Financial Rept B13488, Forwards Bimonthly Progress Rept 21 Re New Switchgear Bldg Const1990-03-30030 March 1990 Forwards Bimonthly Progress Rept 21 Re New Switchgear Bldg Const B13493, Notifies Commission of Amount of Property Insurance Coverage Currently in Force for Util1990-03-30030 March 1990 Notifies Commission of Amount of Property Insurance Coverage Currently in Force for Util B13491, Provides Addl Response to Station Blackout Rule.Utils Have Deligently Attempted to Comply W/Rule Using NUMARC 87-00 Guidelines & Supplementary Guidance1990-03-30030 March 1990 Provides Addl Response to Station Blackout Rule.Utils Have Deligently Attempted to Comply W/Rule Using NUMARC 87-00 Guidelines & Supplementary Guidance B13486, Forwards Rev 2 to Inservice Testing Program, Co Thomas & Safety Evaluation,Per Generic Ltr 89-041990-03-29029 March 1990 Forwards Rev 2 to Inservice Testing Program, Co Thomas & Safety Evaluation,Per Generic Ltr 89-04 B13483, Provides Addl Info to Support 900216 License Amend Request Re Reactor Vessel Matl Surveillance Program,Per 900308 Telcon.Util Planning to Remove Tech Spec Surveillance Capsule Withdrawal Schedule from Tech Specs1990-03-29029 March 1990 Provides Addl Info to Support 900216 License Amend Request Re Reactor Vessel Matl Surveillance Program,Per 900308 Telcon.Util Planning to Remove Tech Spec Surveillance Capsule Withdrawal Schedule from Tech Specs A08574, Ack Receipt of Listed Invoices for Costs Incurred During Reviews of Plants.Fund Will Be wire-transferred on 9004051990-03-29029 March 1990 Ack Receipt of Listed Invoices for Costs Incurred During Reviews of Plants.Fund Will Be wire-transferred on 900405 B13468, Forwards Response to Request for Addl Info Re 10CFR50,App R Compliance Review,Per .Charging Pumps,Equipped W/ fan-cooled Oil Coolers for Use When Component Cooling Water Unavailable,Used During App R Cooldown1990-03-29029 March 1990 Forwards Response to Request for Addl Info Re 10CFR50,App R Compliance Review,Per .Charging Pumps,Equipped W/ fan-cooled Oil Coolers for Use When Component Cooling Water Unavailable,Used During App R Cooldown A08297, Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47. Util Plans to Further Evaluate Effects of Control Sys Failures on Transient,Accidents & core-melt Frequency for Plant Individual Plant Exam1990-03-27027 March 1990 Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47. Util Plans to Further Evaluate Effects of Control Sys Failures on Transient,Accidents & core-melt Frequency for Plant Individual Plant Exam B13478, Submits Draft Emergency Exercise Scenario Package for NRC Review for 900519 Offsite Emergency Preparedness Exercise1990-03-14014 March 1990 Submits Draft Emergency Exercise Scenario Package for NRC Review for 900519 Offsite Emergency Preparedness Exercise ML20012C4511990-03-14014 March 1990 Informs That RB Tourville Has No Need to Maintain License, Effective 900301 ML20012D6251990-03-14014 March 1990 Forwards NPDES Noncompliance Rept Submitted to State of CT ML20012C4401990-03-12012 March 1990 Advises That Licensed Operator OP-10775 Removed from Duty as of 900223 Due to Operator Not Meeting Medical Requirements of 10CFR55.21 B13466, Forwards Reg Guide 1.75 Compliance Review,Per NRC 900122 SER Committing Util to Submit Review in Support of Electrical Design of New Switchgear Bldg at Plant1990-03-0808 March 1990 Forwards Reg Guide 1.75 Compliance Review,Per NRC 900122 SER Committing Util to Submit Review in Support of Electrical Design of New Switchgear Bldg at Plant B13454, Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Approx Two NRC Team Insps Conducted at Facilities Each Yr.Two SSFIs Conducted in 19881990-03-0101 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Approx Two NRC Team Insps Conducted at Facilities Each Yr.Two SSFIs Conducted in 1988 A08496, Ack Receipt of Listed Invoices for Costs Incurred During Routine Reviews of Plant1990-02-15015 February 1990 Ack Receipt of Listed Invoices for Costs Incurred During Routine Reviews of Plant B13445, Forwards Update on Implementation Status of Corrective Actions to SALP Board Recommendations Discussed in 881123 Response & Provides Addl Relevant Info Similar to 890721 Meeting W/Region I Mgt1990-02-14014 February 1990 Forwards Update on Implementation Status of Corrective Actions to SALP Board Recommendations Discussed in 881123 Response & Provides Addl Relevant Info Similar to 890721 Meeting W/Region I Mgt 1990-08-30
[Table view] |
Text
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General Offices e Selden Street, Berlin, Connecticut :
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NsIENIm N(Ua P.O. BOX 270 HARTFORD, CONNECTICUT 06141-o270
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August 30, 1990 s
Docket No. 50-213 B13622
^
h P o c No. 1.19 j
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U.S. Nuclear Regulatory Commission JAttention: Document Control Desk Washington, DC 20555 Gentlemen:
Haddam Neck Plant j
Response to-NRC Staff Request on j
Control Room Design Review 1
Human Enaineerina Discreoancy Resolution This ' submittal ~ forwards' Control Room Design Review (CRDR) Human Engineering:
j Discrepancy (HED) information-for the~Haddam Neck P1 ant, from the Connecticut:
1 Yankee Atomic Power Company.(CYAPCO) to the NRC Staff. ' During our June 13, '
~
- 1990' meeting, CYAPCO: reiterated previous statements' made in the' CRDR Summary.
'l Repor.t, that -the HEDs ? identified would be. resolved utilizing the Integrated
]
. Safety Assessment - Program (ISAP) relative' ranking 3.
At the time of the -
meeting, only a portion:of the HEDs (groups LI-6 containing 317 HEDs) had been-evaluated using the:ISAP' analytical ranking methodology-(ARM), scheduled in the? integrated implementation schedule (IIS) and; reported in tthe AprilL 30, 1990 LISAP) submittal.
The ' balance of ther HEDs. (groups 7-13 containing 131-
- HEDs) wereLundergoing - evaluation a the time and, would be L ranked with the
~ earlier evaluated groups upon - completion.< CYAPC0 committed to communicate-thel results of the initial analytical ranking Lmethodology' (ARM) results tol 1
- he L NRC
- Staff ~ by L August. 30,-1990, stating which. groups of HEDs would..be
'l t
l implemented, and justify 'those groups which would not be implemented.
This ARM L evaluation and the initial ranking ~ have now been completed.. The I
!information which was committed for submittal by' August is contained in the' i
'attachr.ents to this. lette'r; Attachment :1 provides' the' initial. ARM rankings, i
R
- with :the' CRDR topics annotated.. : Attachment : 2. lists' those.' groups of HEDs whichi CYAPC0. is: Jcommitting to implement : : or resolve by some type of-E
, supplemental - action-(i.e.,
p1 ant design-change,
- training, procedure L
modification, etc.). KAttachment 3 addresses those HED groups that CYAPC0~has u,
? judged.'do :not warrant further action. ' Aj =brief : Justification for. : this ~
i _
o positionf s alsor provided.
Additional supporting detail, as' appropriate, i'
lwill be provided in the.ISAP Summary Report scheduled for submittal: by LSeptember 28,~ : 1990.
j l
-We-trust. that this letter fulfills the August 30, 1990 commitment for the 9,
. Haddam: Neck. Plant CRDR information-submittal.
Further CRDR details,
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U.S. Nuclear Regulatory Commission hv
-B13622/Page 2
-August 30,'1990 e
includ'ing the IIS for the later groups, will' be submitted subsequently in tne
~
next41 SAP Summary Report.
If you have any questions-or comments on this information, please contact my istaff.
We remain available to discuss this matter with you at your convenience.
Very truly yours, CONNECTICVT YANKEE ATOMIC. POWER COMPANY f
6 E. 0 f oczka-ff Seniof Vice President cc:
T. T. Martin, NRC Region I Administrator A. B. Wang, NRC Project Manager, Haddam Neck Plant-
'J. T. Shedlosky, NRC Senior Resident Inspector, Haddam Neck Plant C..O. Thomas, NRC Deputy Director, Division of-Licensee Performance and Quality Evaluation
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Page 1 Haddam Neck' Plant ARM Initial Rankinas t
i n
8/16/90 1
1 I
9~
NA00AM ncit ARr, aamiNGs Overall Pelle temenic Persemet Persomet Remainite - 1stal See igAP 8 fitte PA #
tort safety Performence safety Preestivity Project Cost VolWe WetWR 2323 FLW NAP 91N8 SYSTEM AfPLACEMENT 95 065 1
0 768566 1924 10240 308000 54<@6.:e 177.34 2 104 stavlCE Watta tvsttM sutet ANALYSTS 85 000 2
48100 0
480 0
68000 til44.,0 100.44 2
1 02 NIGN\\ LOW PRtslultt valvt INTERLOCKS Lot 3
15794 0
0.5 1280 35000 2 S4.iif 61.61 2
1.19. 9 __ CONTROL ROOM HslGN REvitW Gp 9 88 005 4
2620 880 0.5_
0 11500 4'WS.' 3 37.47 1.19.7 CONTROL Roon MslGN REvitW Go 7 88 005 5
1310 800 0
0 20000 2<dLl.10 13 32 i
1,19.5 CONT RM. Ots. RivitW Gs6 90 020 6
2620 0
0 0
44000 3694.20 8.40 Q09 DN Mov 310 RfPLACEMENT 86 257 7
0 0
1909 1280 52000 3262.06 6.27 1.19.4 COMN. Of S. REVlfW Gp4 90 021 8
1805 9211 9
0 160000 8994.69 5.62 2.114 SW CONTROL SWITCN\\POSlfl0N INDICAfl0N 09 064 9
3938 0
8.5 1280 123000 6267.97 5.10 2.111 ALARA 4GifICAfl0NS 87 044 10 0
0 8600 38400 760000 32644.00 4.30
@9.1 CONI. kM. Ms, RivitW Got 90-019 11 15725 2131 0
1280 570000 24367.95 d.28 1.19.10 CONTROL ROOM MslGN RtyltW Gp 10 88 005 12 2620
_880
- 0.5 0
141000 4309.53 b.06 i-1.'9.12 CONTROL Rom DEslGN RtyttW Go il 88 005 il 2620 880 0
1280 257000 5014.20
.95 1.'9.11 CONTROL Ro0M OtslGN Rtyttw Go 11 88 005 14 1310 880 0
1280 218000 3167.10 1.45 2.' 10 sicutif t COMPutta REPlactMENT 87 010 15 0
0 9
38400 1535000 21132.06 1.38 1.19.8 CONTROL Rom OfSIGN REV1EW Go 8 88 005 16 2620 880 60 0
381000 4229.80 1.11 1.04 stisMIC oual. Of SArtif REL. PIPING 81 05F 17 30650 0
76 1280 4612000 42410.66 0.92 2.115 slit f ACIL618ES Maps.
87 068 18 0
0 0
66560 4837000 36608.00 0.76 1.19.13 CON 1ROL ROOM DislGN RiviaW Gp 13 88 005 19 b
880 0
1200 186000 1320.00 0.71 1.05 tilsMIC situctuRAL MODiflCAtt0Ns 83 036 20_
6356 0
0 0
1521000 8961,96 0.59 1.19.2 CONT. RM. Ms. REYlfW 6p2 88 005 21 15F25 3195 0
0 4600000 24408.75 0.53 2,14 RA01 Afl0N McNitoRING SYsitM UPGRAct 86 043 22
,0 0
8.5 1280 266000 715.39 0.27 l.12 CONTROL Rom NASITA8ttiff 80 113 23 1805 9231 9
0 3389000 8994.69 0.27 1.19.3 CONT. RM. Ots. RivitW 6p3 88 005 24 2620 0
58 0
Sia5uuu 3616.48 0.07 b
l.19.6 CONT. RM. HS Rtyltw sp6 88 005 25 0
0 0
0 65000 0.00 0.00 2.03 400lfl0NAL AfM08PutRIC sitAM OWP 82 192 26 37 0
9 1280 1000000 663.09 0.07
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0 0
0 1280 1000000 704.00 0.07 i.104 CONT.150. VALVE P0s. INDICAfl0N i
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!Page 1 H
Haddam Neck Plant.
ISAP Topic 1.19 Control Room Design Review Groups Which Will be Resolved 1.19.9--Main Control Board Railina ISAP' topic 1.19.9 deals with the installation of-a rail around the Main Control Board (MCB) at the leading edge of the apron section.
Its purpose is "g
--to prevent an operator from inadvertently-operating a control switch on 'the
- lower - portion of the apron while trying to manipulate controls on the vertical section above.
Althouah we have not observed specific instances where this has been a problem, we judge' it appropriate to take action on this-topic.
4,
1.19.7--Imoroved Communications in Breathina Masks ISAP topic 1.19.7 deals with control room operators communicating while wearing respiratory protection.
The project addresses communication aids that will ensure that adequate communications could be carried out while wearing respiratory protection.
The most likely solution here would be a different-type of respirator that includes a communication -device.
Other
. devices, such as ear transceivers or throat microphones were discussed end will be considered.
1.19.5--Master Silence Switch for Noncritical Audible Alarms ISAP Topic 1.19.5 deals with silencing less important main control board-
' annunciators during a significant event.
This involves installation of a switch that would silence these selected annunciators.
l'.19.4--Control Room HVAC Imorovements ISAP Topic 1.19.4 deals with control room ventilation.
This involves upgrading the air conditioning. equipment as necessary to ensure an adequately cooled environment for equipment and personnel.
l.19.1--Additional Benchboard & D/G Control Relocation ISAP Topic 1.19.1 deals with emergency diesel generator controls in the Control Room. -
The controls for starting, stopping and adjusting currently on the auxiliary board in back of the MCB.
This project will r all or part of these controls to the front of the MCB.
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Page 2 l
1.19.10--Auamented Imoortant to Safety Operator Computer Disolay1 ISAP= Topic 1.19.10. deals with control room computer termir.nl displays.
This
- involves development of video display screens that will provide improved parameter indication and monitoring to operators.
.m 1.19.12--Climinate Annunciator Nuisance Alarms i
n ISAP Topic 1.19.12 deals with MCB annunciators.
This will make changes such as elimination of windows with multiple inputs, elimination of nuisance alarms and potentially some relocation of windows.
1.19.11--Correction of Meter and Recorder Scales ISAP Topic 1.19.11 deals with the scales of instruments on the MCB.
This will involve changing scales and perhaps some minor instrument changes to more clearly conform' to NUREG-0700 guidelines.
1.19.8--1ndividual Main Steam line Radiation Monitors ISAP Topic 1.19-8 deals with. steam generator tube rupture (STGR) accident detection and mitigation.
This involves installation of radiation monitoring-instruments on each of. the main steam lines that control room operators ~ could e
use to identify radiation levels in each steam generator.
This topic also considered installation of motor operators on the small main steam nonreturn L
valves, but this will' not be done since the plant operator needs to operate L
other manual valves in this same plant area to isolate a steam generator.
This project will also consider the need for some form of aid to the operator a'
for valve manipulation.
I.19.13--Standardize Control Board Relabellina ISAP Topic 1.19.13 deals with MCB labelling.
This involves upgrading labels L
_ to standard acronyms, conformance with Emergency Operating Procedures, and
~ tandard color coding.
s l'.19.3--Containment Isolation Valves Position Indicatiqn y
ISAP Topic 1.19.3 deals with position indication for Containment Isolation Valves (CIVs).
This will add remote indication for valves that do not i
currently have remote indication.
The scope will likely be limited to Li providing indication on -the primary auxiliary building (PAB) control panel for 10 valves that are in remote areas, i
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Attachment'3 i
-Page 1-t t
Haddam Neck Plant ISAP Topic 1.19 Control Room Design Review Groups Which Do Not Warrant Further Action L
1.19.6--Rewirino Turbine Drain Valve Switches (Stereotvoe)
ISAF Topic 1.19.6 (extremely low initial ranking 25 of 27) deals with the control switches for 'the turbine drain valves.
These switches operate backwards from some others and this topic deals with revising them to make them consistent with others. Operations management has not observed problems with operators manipulating these switches.
In addition, the consequences of operating them incorrectly h6ve no safety significance.
'l.19.2--Modification to 400 Control Room Board Comoonent.1
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ISAP topic 1.19.2 (low ranking 21 of 27) deals with Main Control Board (MCB) indicators and control for. a number of systems including the Reactor, Engineered Safety Features, Chemical and Volume Control, Reactor Coolant and Auxiliary Feedwater.
This group of HEDs, associated with these systems, l
involves a major sequenced relocation of MCB devices so that equi 3 ment.
controls and indicators are arranged in more logical groupings for luman factors consideruions.
- j This topic deals with many important controls and indicators, that would fideally be arranged differently.
As stated in the CRDR Summary Report (pages 32 & 33) the ' core team philosophy during the overall panel enhancement analysis was established to " ensure that the enhanced panels be designed for a newly licensed operator, _with minimal operating experience."
The licensed control room operators have demonstrated their capability over many. years to operate the plant (or the simulator) effectively in both normal and emergency situations with the current control and indicator arrangement.
Operations 1 management' personnel have not observed operator response difficulty related to existing locations of these controls and indicators at the simulator or in l
the plant control room.
The high quality INP0 accredited operator training program (i.e., procedures, staff, simulator, etc.) provide further assurance of the ability of the operators to perform with controls and indicators in
-the existing configuration.
The. low ARM relative ranking combined with the above discussion support and justify the conclusion that the existing -configuration is acceptable and no further rearrangement action is warranted with one exception.
During the resolution (i.e., evaluation, engineering, design, installation and - testing of design modifications) of the current Auxiliary Feedwater (AFW) system issue, -which was described in our correspondence to you dated August 25, 1990, applicable portions of this topic will be resolved to the degree feasible. Our objective will be to maximize the safety benefit to be derived from these enhancements without incurring the total estimated project cost of
$4.6 million.