| 05000213/LER-1982-004, Forwards LER 82-004/01T-0 | 18 June 1982 | Forwards LER 82-004/01T-0 | |
| 05000213/LER-1982-005, Forwards LER 82-005/03L-0 | 9 June 1982 | Forwards LER 82-005/03L-0 | |
| 05000213/LER-1989-020, Forwards LER 89-020-01 Which Updates Info Re Fuel Failures Discovered During 1989 Refueling Outage & Identified as Potential Issue in Recent Nrc'S Historical Review Rept. Conclusion from Original LER Remains Unchanged | 4 June 1998 | Forwards LER 89-020-01 Which Updates Info Re Fuel Failures Discovered During 1989 Refueling Outage & Identified as Potential Issue in Recent Nrc'S Historical Review Rept. Conclusion from Original LER Remains Unchanged | |
| 05000213/LER-1996-016, Forwards LER 96-016-01 & LER 96-027-01,retracting Originally Proposed Corrective Actions That Will No Longer Be Implemented as Result of CYAPCO Decision to Cease Operations at Haddam Neck Plant | 15 September 1997 | Forwards LER 96-016-01 & LER 96-027-01,retracting Originally Proposed Corrective Actions That Will No Longer Be Implemented as Result of CYAPCO Decision to Cease Operations at Haddam Neck Plant | |
| 05000213/LER-1996-030, Forwards Suppl LERs 94-015-02,96-019-01,95-001-02,96-021-01, 96-005-01,96-030-01,96-013-01 & 97-003-01 to Retract Originally Proposed CAs That Are No Longer Implemented. Proprietary Page 15 of 15 to LER 96-030-01,encl | 5 September 1997 | Forwards Suppl LERs 94-015-02,96-019-01,95-001-02,96-021-01, 96-005-01,96-030-01,96-013-01 & 97-003-01 to Retract Originally Proposed CAs That Are No Longer Implemented. Proprietary Page 15 of 15 to LER 96-030-01,encl | |
| A01328, Forwards Response to SER Open Items Re NUREG-0737,Item II.B.1, Reactor Coolant Sys Vents & Insp Rept 50-336/84-07 | 25 November 1987 | Forwards Response to SER Open Items Re NUREG-0737,Item II.B.1, Reactor Coolant Sys Vents & Insp Rept 50-336/84-07 | Hot Short |
| A01395, Advises That Inservice Date for Containment Level Detection Sys Is Postponed Until 830101,in Response to IE Bulletin 80-24, Prevention of Damage Due to Water Leakage Inside Containment. | 1 June 1982 | Advises That Inservice Date for Containment Level Detection Sys Is Postponed Until 830101,in Response to IE Bulletin 80-24, Prevention of Damage Due to Water Leakage Inside Containment. | |
| A01701, Forwards Natural Circulation Test at CT Yankee Nuclear Power Plant, Demonstrating Ability of Facility to Undergo Sustained Natural Circulation Cooldown W/O Formation of Steam Bubble in Reactor Vessel Upper Head Region | 9 June 1982 | Forwards Natural Circulation Test at CT Yankee Nuclear Power Plant, Demonstrating Ability of Facility to Undergo Sustained Natural Circulation Cooldown W/O Formation of Steam Bubble in Reactor Vessel Upper Head Region | |
| A02375, Forwards Supplemental Info in Response to Generic Ltr 82-05 Re Status of NUREG-0737,Items II.B.2, Plant Shielding, II.B.3, Post-Accident Sampling, II.F.1.1,II.F.1.2 & II.F.1.6, Effluent & Hydrogen Monitoring | 10 June 1982 | Forwards Supplemental Info in Response to Generic Ltr 82-05 Re Status of NUREG-0737,Items II.B.2, Plant Shielding, II.B.3, Post-Accident Sampling, II.F.1.1,II.F.1.2 & II.F.1.6, Effluent & Hydrogen Monitoring | |
| A02398, Clarifies Training & Experience of Shift Technical Advisors, Per NRC Re Util 801231 & 820219 Responses to NUREG-0737,Item I.A.1.1.One Advisor Does Not Hold Current Senior Reactor Operator License.Nureg Requirements Met | 23 June 1982 | Clarifies Training & Experience of Shift Technical Advisors, Per NRC Re Util 801231 & 820219 Responses to NUREG-0737,Item I.A.1.1.One Advisor Does Not Hold Current Senior Reactor Operator License.Nureg Requirements Met | |
| A02425, Responds to NRC Re Violations Noted in IE Insp Rept 50-213/82-07.Corrective Actions:Monthly Check of Power Operated Relief Valve & Safety Valve Position Indication Being Performed.Test Procedure Sur 5.1-15 Will Be Revised | 14 May 1982 | Responds to NRC Re Violations Noted in IE Insp Rept 50-213/82-07.Corrective Actions:Monthly Check of Power Operated Relief Valve & Safety Valve Position Indication Being Performed.Test Procedure Sur 5.1-15 Will Be Revised | |
| A02437, Informs That NRC 820414 Draft Evaluation of SEP Topic VI-7.B Re ESF Switchover from Injection to Recirculation Mode Should Be Revised Based on Licensee .Submitted Comments Should Be Incorporated Into Evaluation | 1 July 1982 | Informs That NRC 820414 Draft Evaluation of SEP Topic VI-7.B Re ESF Switchover from Injection to Recirculation Mode Should Be Revised Based on Licensee .Submitted Comments Should Be Incorporated Into Evaluation | |
| A02441, Submits CT Yankee Atomic Power Co Comments on Draft SEP Operating Experience Rept,Sections 4.2 & 4.5.1.1 | 22 June 1982 | Submits CT Yankee Atomic Power Co Comments on Draft SEP Operating Experience Rept,Sections 4.2 & 4.5.1.1 | |
| A02452, Forwards Responses to 820414 Request for Info Re Secondary Water Chemistry Control Program.Data Reviewed by Corporate Chemistry Group for long-term Trend Analysis | 7 July 1982 | Forwards Responses to 820414 Request for Info Re Secondary Water Chemistry Control Program.Data Reviewed by Corporate Chemistry Group for long-term Trend Analysis | |
| A02468, Comments on Draft Branch Technical Position Re Radwaste Classification | 10 May 1982 | Comments on Draft Branch Technical Position Re Radwaste Classification | |
| A02469, Responds to NRC Re Violations Noted in IE Insp Rept 50-213/82-14.Corrective actions:call-up Method of Staffing Technical Support Ctr Will Be Formalized by 820715 & Emergency Planning Coordinator Appointed | 28 May 1982 | Responds to NRC Re Violations Noted in IE Insp Rept 50-213/82-14.Corrective actions:call-up Method of Staffing Technical Support Ctr Will Be Formalized by 820715 & Emergency Planning Coordinator Appointed | |
| A02477, Forwards Response to Generic Ltr 82-10 Requesting Info Re Implementation Dates for Selected TMI Action Plan Items in NUREG-0737 | 4 June 1982 | Forwards Response to Generic Ltr 82-10 Requesting Info Re Implementation Dates for Selected TMI Action Plan Items in NUREG-0737 | |
| A02608, Submits Addl Clarifications of 820301 App R Review for Facilities,In Response to NRC 820625 & 0707 Requests | 30 July 1982 | Submits Addl Clarifications of 820301 App R Review for Facilities,In Response to NRC 820625 & 0707 Requests | |
| A02611, Informs That Documentation for Compliance w/NUREG-0737,Item II.B.3 Criterion Re post-accident Sampling Sys Will Be Provided by 820917 | 19 July 1982 | Informs That Documentation for Compliance w/NUREG-0737,Item II.B.3 Criterion Re post-accident Sampling Sys Will Be Provided by 820917 | |
| A02644, Submits Comments on SEP Phase Ii,To Assist NRC in Development of Proposed Program for Phase III | 30 July 1982 | Submits Comments on SEP Phase Ii,To Assist NRC in Development of Proposed Program for Phase III | |
| A03104, Responds to NRC Re Violations Noted in IE Insp Rept 50-213/83-06.Corrective Actions:Cure Time for Drums of Solidified Waste Increased to 7 Days & Independent Check for Residual Water Performed | 7 April 1983 | Responds to NRC Re Violations Noted in IE Insp Rept 50-213/83-06.Corrective Actions:Cure Time for Drums of Solidified Waste Increased to 7 Days & Independent Check for Residual Water Performed | |
| A04500, Provides Addl Info to Amend Proposed Tech Specs on Flammable Liquid Control for Control Room,Per 850724 Telcon.Definition of Suitable Containers Consistent w/820716 Submittal & Section 2.2 of SER Issued W/Exemptions from 10CFR50,App R | 1 August 1985 | Provides Addl Info to Amend Proposed Tech Specs on Flammable Liquid Control for Control Room,Per 850724 Telcon.Definition of Suitable Containers Consistent w/820716 Submittal & Section 2.2 of SER Issued W/Exemptions from 10CFR50,App R | Exemption Request
Fire Watch |
| A04547, Informs of Status of Commitments in Response to Facility Proposed Design Change Task Group Final Rept,Per . All Commitments Fulfilled.Original Intent of Improvement Plans Unaltered | 26 June 1986 | Informs of Status of Commitments in Response to Facility Proposed Design Change Task Group Final Rept,Per . All Commitments Fulfilled.Original Intent of Improvement Plans Unaltered | |
| A04582, Clarifies Commitment in 850225 Response to Insp Rept 50-213/84-26.All Components Listed in Mepl Will Have Production Maint Mgt Sys QA Indicators Verified as Properly Reflecting QA Status | 21 November 1985 | Clarifies Commitment in 850225 Response to Insp Rept 50-213/84-26.All Components Listed in Mepl Will Have Production Maint Mgt Sys QA Indicators Verified as Properly Reflecting QA Status | Fire Protection Program |
| A04790, Requests Extension to 860104 for Haddam Neck Re Environ Qualification of Electrical Equipment,Per Generic Ltr 85-15, 10CFR50.49(g) & Integrated Safety Assessment Program.Further Evaluation Proposed for Millstone.Fee Paid | 30 September 1985 | Requests Extension to 860104 for Haddam Neck Re Environ Qualification of Electrical Equipment,Per Generic Ltr 85-15, 10CFR50.49(g) & Integrated Safety Assessment Program.Further Evaluation Proposed for Millstone.Fee Paid | Reactor Vessel Water Level
Anchor Darling
Exemption Request
Backfit |
| A04820, Forwards Rev 0 to Nuclear Engineering & Operating Procedure Neo 2.17, Secondary Water Chemistry Program, Per Generic Ltr 85-02 Request for Description of Overall Program for Assuring Steam Generator Tube Integrity | 25 June 1985 | Forwards Rev 0 to Nuclear Engineering & Operating Procedure Neo 2.17, Secondary Water Chemistry Program, Per Generic Ltr 85-02 Request for Description of Overall Program for Assuring Steam Generator Tube Integrity | Foreign Material Exclusion |
| A04824, Submits ATWS Rule Schedule Required by 10CFR50.62(d),per Generic Ltr 85-06.Facilities Participating in NRC Integrated Safety Assessment Program.Justification for Absence of Schedules for Haddam Neck & Millstone Unit 1 Provided | 11 October 1985 | Submits ATWS Rule Schedule Required by 10CFR50.62(d),per Generic Ltr 85-06.Facilities Participating in NRC Integrated Safety Assessment Program.Justification for Absence of Schedules for Haddam Neck & Millstone Unit 1 Provided | Hydrostatic
Backfit |
| A04858, Requests Exemption from Schedular Requirements of 10CFR50.71 Re FSAR Updates,Due to Significant Burden on Engineering Resources.Fsar Update Efforts Listed.Fee Paid | 13 September 1985 | Requests Exemption from Schedular Requirements of 10CFR50.71 Re FSAR Updates,Due to Significant Burden on Engineering Resources.Fsar Update Efforts Listed.Fee Paid | Probabilistic Risk Assessment
Exemption Request |
| A04872, Informs That NRC Misinterpreted 841004 Proposed Resolution of NUREG-0737,Item II.K.3.25 Re Loss of Ac Power on Reactor Coolant Pump Seals.Util Commitment Was to Evaluate Change in Integrated Safety Assessment Program | 3 June 1985 | Informs That NRC Misinterpreted 841004 Proposed Resolution of NUREG-0737,Item II.K.3.25 Re Loss of Ac Power on Reactor Coolant Pump Seals.Util Commitment Was to Evaluate Change in Integrated Safety Assessment Program | |
| A04880, Responds to Generic Ltr 85-07 Re Implementation of Integrated Schedule for Plant Mods.Integrated Schedules Endorsed.Integrated Safety Assessment Program Evaluation Process Will Also Be Applied to Millstone 2 | 5 August 1985 | Responds to Generic Ltr 85-07 Re Implementation of Integrated Schedule for Plant Mods.Integrated Schedules Endorsed.Integrated Safety Assessment Program Evaluation Process Will Also Be Applied to Millstone 2 | Backfit |
| A04905, Responds to NRC Re Violations Noted in Insp Rept 50-213/85-03.Corrective Actions:Calibr Procedures Revised, Procedure IC-P-2 Implemented & Plot Developed,Indicating Loop Delta P | 28 May 1985 | Responds to NRC Re Violations Noted in Insp Rept 50-213/85-03.Corrective Actions:Calibr Procedures Revised, Procedure IC-P-2 Implemented & Plot Developed,Indicating Loop Delta P | |
| A04906, Forwards Response to SALP Repts for 18-month Period Ending 850228,per 850604 Meeting W/Nrc.Util Initiatives to Reemphasize Importance of Quality in Design Change Activities Listed | 5 July 1985 | Forwards Response to SALP Repts for 18-month Period Ending 850228,per 850604 Meeting W/Nrc.Util Initiatives to Reemphasize Importance of Quality in Design Change Activities Listed | Fire Barrier
Systematic Assessment of Licensee Performance |
| A04919, Responds to NRC Re Violations Noted in Insp Rept 50-213/85-08.Corrective Actions:Review Conducted to Ensure Environ Review Board Audits Subsequent to 1983 Complete | 20 June 1985 | Responds to NRC Re Violations Noted in Insp Rept 50-213/85-08.Corrective Actions:Review Conducted to Ensure Environ Review Board Audits Subsequent to 1983 Complete | |
| A04948, Forwards Clarifications of Rev 11 to Modified Amended Security Plan,Per 850612 & 19 Commitments.Clarifications Withheld (Ref 10CFR73.21 & 2.790) | 28 June 1985 | Forwards Clarifications of Rev 11 to Modified Amended Security Plan,Per 850612 & 19 Commitments.Clarifications Withheld (Ref 10CFR73.21 & 2.790) | |
| A05012, Responds to NRC Re Violations Noted in Insp Rept 50-213/85-09.Corrective Actions:Procedure ACP 1.2-7.1 Re Receipt,Insp & Identification of Matls,Parts & Components Revised to Clarify QA Responsibilities of Personnel | 26 July 1985 | Responds to NRC Re Violations Noted in Insp Rept 50-213/85-09.Corrective Actions:Procedure ACP 1.2-7.1 Re Receipt,Insp & Identification of Matls,Parts & Components Revised to Clarify QA Responsibilities of Personnel | |
| A05034, Forwards Addl Info Re Manual Trip of Reactor Coolant Pumps, Per NRC Request.Westinghouse Owners Group Methodology Being Used on Interim Basis Until Revised Small Break LOCA Analysis Approved by NRC | 5 March 1987 | Forwards Addl Info Re Manual Trip of Reactor Coolant Pumps, Per NRC Request.Westinghouse Owners Group Methodology Being Used on Interim Basis Until Revised Small Break LOCA Analysis Approved by NRC | |
| A05041, Forwards Review of Isap Topic 1.21, Reg Guide 1.97 Instrumentation, Per 850517 Commitment.Nrc 850703 Concerns Re Status of Compliance W/Rev 2 to Reg Guide 1.97 Also Addressed | 30 September 1986 | Forwards Review of Isap Topic 1.21, Reg Guide 1.97 Instrumentation, Per 850517 Commitment.Nrc 850703 Concerns Re Status of Compliance W/Rev 2 to Reg Guide 1.97 Also Addressed | Boric Acid
Anticipated operational occurrence |
| A05050, Submits Licensed Operator Requalification Program Status Rept.Summary of 850628 Requalification Training Meeting Rept 50-213/85-01 Was Provided to Document Commitments Listed | 26 July 1985 | Submits Licensed Operator Requalification Program Status Rept.Summary of 850628 Requalification Training Meeting Rept 50-213/85-01 Was Provided to Document Commitments Listed | |
| A05084, Submits Final Response to IE Bulletin 80-11 Re Masonry Wall Design.Cracks Monitored Over 1-month Span.Review of as-built Wall Before Mods Indicates No Cracks.Mortar Joint Cracks Resulted from Const Process of Installing Mods | 18 February 1986 | Submits Final Response to IE Bulletin 80-11 Re Masonry Wall Design.Cracks Monitored Over 1-month Span.Review of as-built Wall Before Mods Indicates No Cracks.Mortar Joint Cracks Resulted from Const Process of Installing Mods | |
| A05085, Notifies of Change in 850816 Commitment to Provide Improved Plant Operations Review Committee Review of Plant Design Change Records in Response to Insp 50-213/85-15.Commitment Now Considered W/O Merit & Therefore Eliminated | 18 September 1987 | Notifies of Change in 850816 Commitment to Provide Improved Plant Operations Review Committee Review of Plant Design Change Records in Response to Insp 50-213/85-15.Commitment Now Considered W/O Merit & Therefore Eliminated | |
| A05276, Forwards Safety & Safeguards Insp Fees for 841223-850330 | 23 October 1985 | Forwards Safety & Safeguards Insp Fees for 841223-850330 | |
| A05382, Forwards Page 3-3 of Approved Modified Amended Security Plan (Masp).Rev 11 Change to Section 3.3.1.1 of Msap Withdrawn. Page Withheld (Ref 10CFR73.21) | 8 May 1986 | Forwards Page 3-3 of Approved Modified Amended Security Plan (Masp).Rev 11 Change to Section 3.3.1.1 of Msap Withdrawn. Page Withheld (Ref 10CFR73.21) | |
| A05384, Responds to NRC Re Violations Noted in Meeting Rept 50-213/85-22.Corrective Actions:Design Change Installation Controls & Testing Requirements Improved & Previous Mods to Auxiliary Feedwater Sys Wiring Verified | 16 December 1985 | Responds to NRC Re Violations Noted in Meeting Rept 50-213/85-22.Corrective Actions:Design Change Installation Controls & Testing Requirements Improved & Previous Mods to Auxiliary Feedwater Sys Wiring Verified | |
| A05394, Forwards Final Summary Rept Addressing IE Bulletin 85-003, Motor-Operated Valve Common Mode Failures. No Addl Work W/ Respect to Bulletin Suppl Necessary for Millstone Unit 1 | 27 June 1988 | Forwards Final Summary Rept Addressing IE Bulletin 85-003, Motor-Operated Valve Common Mode Failures. No Addl Work W/ Respect to Bulletin Suppl Necessary for Millstone Unit 1 | Boric Acid
Stroke time |
| A05420, Forwards Addl Info Supporting Util 850916 Request for Exemption from Fire Protection Requirements of 10CFR50, App R,Per NRC 851204 Request.Verbal Responses Provided to NRC During 851210 Site Visit | 19 February 1986 | Forwards Addl Info Supporting Util 850916 Request for Exemption from Fire Protection Requirements of 10CFR50, App R,Per NRC 851204 Request.Verbal Responses Provided to NRC During 851210 Site Visit | Safe Shutdown
Fire Barrier
Exemption Request |
| A05434, Forwards Util Implementation Ltr Rept Re Inadequate Core Cooling (ICC) Instrumentation Sys,As Committed in Util 850201 Submittal.Spds ICC Display Will Be Confirmed in Informational Ltr After Implementation of SPDS | 18 September 1986 | Forwards Util Implementation Ltr Rept Re Inadequate Core Cooling (ICC) Instrumentation Sys,As Committed in Util 850201 Submittal.Spds ICC Display Will Be Confirmed in Informational Ltr After Implementation of SPDS | |
| A05442, Submits Addl Info Re Compliance W/Atws Rule Schedule,Per 10CFR50.62,in Context of Isap.Isap Review Will Be Submitted by 860625.Request for Permanent Exemption Will Be Submitted by 860530 | 18 February 1986 | Submits Addl Info Re Compliance W/Atws Rule Schedule,Per 10CFR50.62,in Context of Isap.Isap Review Will Be Submitted by 860625.Request for Permanent Exemption Will Be Submitted by 860530 | Exemption Request |
| A05457, Forwards Results of RCS Seismic Reevaluations & Final Plans for Mods Identified in NRC Safety Evaluation of SEP Topic III-6.All Outstanding Issues Re Generic Ltr 84-04 & SEP Topic III-6 Resolved | 1 May 1987 | Forwards Results of RCS Seismic Reevaluations & Final Plans for Mods Identified in NRC Safety Evaluation of SEP Topic III-6.All Outstanding Issues Re Generic Ltr 84-04 & SEP Topic III-6 Resolved | |
| A05515, Responds to Violations Noted in Insp Rept 50-213/85-21. Corrective Actions:Station Supervisor Directed to Apply Disciplinary Action in Cases of Willful & Knowledgeable Noncompliance W/Procedure | 28 February 1986 | Responds to Violations Noted in Insp Rept 50-213/85-21. Corrective Actions:Station Supervisor Directed to Apply Disciplinary Action in Cases of Willful & Knowledgeable Noncompliance W/Procedure | Shutdown Margin |
| A05610, Responds to Generic Ltr 86-04 Re Policy Statement on Engineering Expertise on Shift.Comparison of INPO Shift Technical Advisor Guidelines W/Established Bachelors Degree Programs in Engineering Encl | 13 June 1986 | Responds to Generic Ltr 86-04 Re Policy Statement on Engineering Expertise on Shift.Comparison of INPO Shift Technical Advisor Guidelines W/Established Bachelors Degree Programs in Engineering Encl | Reactor Vessel Water Level
Ultimate heat sink
Fuel cladding
Power change |