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	Issue date	Title	Topic
A08899, Responds to NRC Re Unresolved Item Noted in Insp Rept 50-213/90-08.Corrective Actions:Radiation Detector Installed in Control Room Ventilation Sys	19 October 1990	Responds to NRC Re Unresolved Item Noted in Insp Rept 50-213/90-08.Corrective Actions:Radiation Detector Installed in Control Room Ventilation Sys
A10848, Forwards Copy of Agreement Entered Into Between Northeast Utilities & PM Blanch,In Response to 930211 Request. Agreement Withheld,Per 10CFR2.790	12 February 1993	Forwards Copy of Agreement Entered Into Between Northeast Utilities & PM Blanch,In Response to 930211 Request. Agreement Withheld,Per 10CFR2.790
B10428, Comments on Systematic Assessment of Licensee Performance for Jul 1980-June 1981,discussed During 820209 Meeting.Mgt Action Will Be Taken Re Surveillance Activities to Achieve Improved Performance	9 March 1982	Comments on Systematic Assessment of Licensee Performance for Jul 1980-June 1981,discussed During 820209 Meeting.Mgt Action Will Be Taken Re Surveillance Activities to Achieve Improved Performance	Systematic Assessment of Licensee Performance
B10525, Discusses Mods to Assure That Control Room Remains Habitable Under All Accident Conditions Per TMI Action Item III.D.3.4. Radiation Detector in Outside Air Intake & Smoke Detector in Control Room Air Intake Should Be Included	8 July 1982	Discusses Mods to Assure That Control Room Remains Habitable Under All Accident Conditions Per TMI Action Item III.D.3.4. Radiation Detector in Outside Air Intake & Smoke Detector in Control Room Air Intake Should Be Included
B10530, Provides Revised Schedule for Submittal of plant-specific Repts,Per NUREG-0737,Item II.D.1 Relief & Safety Valve Testing Requirements.Valves Tested in EPRI Program Adequately Represent Safety & Relief Valves Used	9 July 1972	Provides Revised Schedule for Submittal of plant-specific Repts,Per NUREG-0737,Item II.D.1 Relief & Safety Valve Testing Requirements.Valves Tested in EPRI Program Adequately Represent Safety & Relief Valves Used
B10532, Forwards Revision 8 to Modified Amended Security Plan. Revision Withheld (Ref 10CFR2.790 & 10CFR73.21(b))	12 July 1982	Forwards Revision 8 to Modified Amended Security Plan. Revision Withheld (Ref 10CFR2.790 & 10CFR73.21(b))
B10541, Notifies of Delay in Submittal of Head Vent Procedures Until 820901	30 July 1982	Notifies of Delay in Submittal of Head Vent Procedures Until 820901
B10755, Forwards Public Version of Rev 13 to Emergency Plan Implementing Procedures EPIP 1.5-2, Notification & Communication & EPIP 1.5-41 Re Core Damage Estimate.W/O Procedure 1.5-41	12 April 1983	Forwards Public Version of Rev 13 to Emergency Plan Implementing Procedures EPIP 1.5-2, Notification & Communication & EPIP 1.5-41 Re Core Damage Estimate.W/O Procedure 1.5-41
B11103, Forwards Draft Exercise Controllers Manual for 840512-14 full-scale Emergency Preparedness Exercise at Plant	28 March 1984	Forwards Draft Exercise Controllers Manual for 840512-14 full-scale Emergency Preparedness Exercise at Plant
B11211, Requests Rev to Carbon Copy Listing for NRR Correspondence to Reflect Change of Address for Outside Recipient	7 June 1984	Requests Rev to Carbon Copy Listing for NRR Correspondence to Reflect Change of Address for Outside Recipient
B11313, Submits Addl Justification or Clarification for 10 Open Items from SER for SEP Topic III-5.A, High Energy Pipe Break Inside Containment, Per Section 4.8 of NUREG-0826, Integrated Plant Safety Assessment,Haddam Neck Plant	17 December 1984	Submits Addl Justification or Clarification for 10 Open Items from SER for SEP Topic III-5.A, High Energy Pipe Break Inside Containment, Per Section 4.8 of NUREG-0826, Integrated Plant Safety Assessment,Haddam Neck Plant	Safe Shutdown
B11409, Responds to IE Bulletin 80-06, ESF Reset Control. Trip Signal to Containment Air Activity Pump & Containment Sump Pump Provided.Removal of Safety Injection Actuation Signals from RHR Valves Being Evaluated	28 April 1986	Responds to IE Bulletin 80-06, ESF Reset Control. Trip Signal to Containment Air Activity Pump & Containment Sump Pump Provided.Removal of Safety Injection Actuation Signals from RHR Valves Being Evaluated
B11411, Discusses SALP for Facilities.Input to SALP Evaluation Process & Followup to Previous SALP Rept Actions Encl	22 March 1985	Discusses SALP for Facilities.Input to SALP Evaluation Process & Followup to Previous SALP Rept Actions Encl	Systematic Assessment of Licensee Performance Biofouling
B11423, Comments on Notice of Proposed Rulemaking Re Backfitting Isap Consistent W/Commission Majority View Re Proposed Backfit Rule.Current Plans Re Pilot Program Appropriate	23 January 1985	Comments on Notice of Proposed Rulemaking Re Backfitting Isap Consistent W/Commission Majority View Re Proposed Backfit Rule.Current Plans Re Pilot Program Appropriate	Backfit
B11525, Suppls 850128 Response to Insp Rept 50-213/84-28 & 841213 Order Modifying License Re Failure of Reactor Cavity Seal Ring.Possible Misinterpretation of 850128 Response Re Design Changes Deemed Significant Clarified	28 May 1985	Suppls 850128 Response to Insp Rept 50-213/84-28 & 841213 Order Modifying License Re Failure of Reactor Cavity Seal Ring.Possible Misinterpretation of 850128 Response Re Design Changes Deemed Significant Clarified
B11536, Informs That Combustible Gas Detectors in Chemistry Lab Not Tested or Calibr Per Manufacturer Spec.Detector Sys Turned Over to Plant Operations & Maint Depts.Detectors Will Be Tested & Calibr Prior to Return to Svc	30 August 1985	Informs That Combustible Gas Detectors in Chemistry Lab Not Tested or Calibr Per Manufacturer Spec.Detector Sys Turned Over to Plant Operations & Maint Depts.Detectors Will Be Tested & Calibr Prior to Return to Svc	Safe Shutdown Fire Protection Program
B11537, Responds to 850402 Request for Addl Info Re Integrated Safety Assessment Program (Isap) Review.Description of All Plant Betterment Projects & Engineering Studies to Be Included in Isap Review Encl	17 May 1985	Responds to 850402 Request for Addl Info Re Integrated Safety Assessment Program (Isap) Review.Description of All Plant Betterment Projects & Engineering Studies to Be Included in Isap Review Encl	Safe Shutdown Reactor Vessel Water Level Tornado Missile Safe Shutdown Earthquake Weld Overlay Coatings Tornado Generated Missile Tornado Missile Protection Exemption Request Earthquake Control of Heavy Loads Biofouling Backfit
B11546, Discusses Intended Applications of Drillco Maxi-Bolt Concrete Anchors.Ie Bulletin 79-02 Factor of Safety Used to Compensate for Uncertainty in Load Carrying Capability Due to Friction Between Expansion Anchor Bolt Wedge & Concrete	29 May 1985	Discusses Intended Applications of Drillco Maxi-Bolt Concrete Anchors.Ie Bulletin 79-02 Factor of Safety Used to Compensate for Uncertainty in Load Carrying Capability Due to Friction Between Expansion Anchor Bolt Wedge & Concrete
B11550, Advises That Proposed Tech Spec Revs Re Limiting Overtime for Persons Performing safety-related Functions Currently Under Review & Approval.Proposed Changes Will Be Submitted by 850630	24 May 1985	Advises That Proposed Tech Spec Revs Re Limiting Overtime for Persons Performing safety-related Functions Currently Under Review & Approval.Proposed Changes Will Be Submitted by 850630
B11567, Forwards NPDES Monthly Discharge Monitoring Rept for Sept 1997.Addl Samples Taken at NPDES Locations & Analyzed W/ Approved Methods Included in Table 2 & 3	27 October 1997	Forwards NPDES Monthly Discharge Monitoring Rept for Sept 1997.Addl Samples Taken at NPDES Locations & Analyzed W/ Approved Methods Included in Table 2 & 3
B11581, Informs That Schedule for Human Factors Review for Fire Protection Will Be Included in Control Room Design Review Program.Review Performed Per Suppl 1 to NUREG-0737.Safe Shutdown Procedures Will Be Implemented Following Mods	1 July 1985	Informs That Schedule for Human Factors Review for Fire Protection Will Be Included in Control Room Design Review Program.Review Performed Per Suppl 1 to NUREG-0737.Safe Shutdown Procedures Will Be Implemented Following Mods	Safe Shutdown
B11583, Provides Info Re Activities Currently Planned for 1986 Refueling Outage,Assuring Continued Operability of Steam Generators.Application to Amend License DPR-61 Will Be Submitted by 851001 to Support Sleeving During Outage	19 July 1985	Provides Info Re Activities Currently Planned for 1986 Refueling Outage,Assuring Continued Operability of Steam Generators.Application to Amend License DPR-61 Will Be Submitted by 851001 to Support Sleeving During Outage
B11585, Submits Revised Commitment on SEP Topic III-10.A,per Section 4.13 of Integrated Plant Safety Assessment Rept (NUREG-0826),concerning Mods to Butterfly Type Motor Operated Valves Utilized in Svc Water Sys	27 June 1985	Submits Revised Commitment on SEP Topic III-10.A,per Section 4.13 of Integrated Plant Safety Assessment Rept (NUREG-0826),concerning Mods to Butterfly Type Motor Operated Valves Utilized in Svc Water Sys
B11586, Forwards Addl Info Re NUREG-0737,Item II.F.1.6, Containment Hydrogen Monitoring Sys, for Millstone Unit 1 & Documents Telcons Re Items II.F.1.4 & II.F.1.5 for Haddam Neck Plant	5 July 1985	Forwards Addl Info Re NUREG-0737,Item II.F.1.6, Containment Hydrogen Monitoring Sys, for Millstone Unit 1 & Documents Telcons Re Items II.F.1.4 & II.F.1.5 for Haddam Neck Plant
B11587, Forwards Rev 3 to Safety-Related Piping Seismic Qualification Program, Per SEP Topic III.6.Changes to Damping Values,Peak Shifting & Independent Support Motion Described	27 June 1985	Forwards Rev 3 to Safety-Related Piping Seismic Qualification Program, Per SEP Topic III.6.Changes to Damping Values,Peak Shifting & Independent Support Motion Described	Backfit
B11591, Responds to NRC 850618 Request for Addl Info Re 850611 Proposed Rev to Section 3.4 of Tech Specs Re Pressure/Temp Limits.Revised Figures 3.4-1,3.4-8 & 3.4-9 Encl.Amend to License DPR-61 Still Required by 850720	27 June 1985	Responds to NRC 850618 Request for Addl Info Re 850611 Proposed Rev to Section 3.4 of Tech Specs Re Pressure/Temp Limits.Revised Figures 3.4-1,3.4-8 & 3.4-9 Encl.Amend to License DPR-61 Still Required by 850720	Hydrostatic
B11599, Forwards USGS Info Re SEP Topic II-3.B, Flooding Potential & Protection Requirements, Per 850530 Request.Info Consists of Connecticut River Rating Table at Bodkin Rock & Indicates That Stage Elevation Affected by Tidal Effects Up to 8.0 Ft	1 July 1985	Forwards USGS Info Re SEP Topic II-3.B, Flooding Potential & Protection Requirements, Per 850530 Request.Info Consists of Connecticut River Rating Table at Bodkin Rock & Indicates That Stage Elevation Affected by Tidal Effects Up to 8.0 Ft
B11603, Clarifies Misinterpretations of Re Insp Rept 50-213/85-07.Ltr Discussed Measures Planned to Approve Coordination & Technical Review of Submittals to Nrc.No Specific Procedures to Fulfill Objective Implemented	5 July 1985	Clarifies Misinterpretations of Re Insp Rept 50-213/85-07.Ltr Discussed Measures Planned to Approve Coordination & Technical Review of Submittals to Nrc.No Specific Procedures to Fulfill Objective Implemented
B11617, Provides Comments on Draft NUREG-0844, NRC Integrated Program for Resolution of Unresolved Safety Issues A-3,A-4 & A-5 Re Steam Generator Tube Integrity, in Response to Generic Ltr 85-02	29 July 1985	Provides Comments on Draft NUREG-0844, NRC Integrated Program for Resolution of Unresolved Safety Issues A-3,A-4 & A-5 Re Steam Generator Tube Integrity, in Response to Generic Ltr 85-02
B11625, Advises That Util Plans to Implement Encl Curves, Representing Planned Means for Compliance w/10CFR50,App G Between 14.0 & 22.0 EFPY When Current Curves for Heatup & Cooldown Become Valid at 14.0 EFPY	17 July 1985	Advises That Util Plans to Implement Encl Curves, Representing Planned Means for Compliance w/10CFR50,App G Between 14.0 & 22.0 EFPY When Current Curves for Heatup & Cooldown Become Valid at 14.0 EFPY	Hydrostatic
B11629, Advises That Util Unable to Meet Jul 1985 Schedule for Submittal of Amend to License DPR-61 Re post-accident Sampling Sys Containment Isolation Valves.Amend Request Will Be Submitted During Third Quarter 1985	30 July 1985	Advises That Util Unable to Meet Jul 1985 Schedule for Submittal of Amend to License DPR-61 Re post-accident Sampling Sys Containment Isolation Valves.Amend Request Will Be Submitted During Third Quarter 1985	Systematic Assessment of Licensee Performance
B11636, Clarifies Status of Encl Proposed Tech Spec Changes,Per 850709 Response to Generic Ltr 83-43 Re Reporting Requirements of 10CFR50.72 & 73.Submittal Supersedes May 1983 Proposed Tech Spec Section 6.9 Changes	15 August 1985	Clarifies Status of Encl Proposed Tech Spec Changes,Per 850709 Response to Generic Ltr 83-43 Re Reporting Requirements of 10CFR50.72 & 73.Submittal Supersedes May 1983 Proposed Tech Spec Section 6.9 Changes
B11643, Forwards Info Re Control Room Halon Fire Suppression Sys,In Response to 850715 Request.Total Flooding of Halon Sys Will Be Installed in Facility Control Room During Next Refueling Outage,Per 10CFR50.48 Schedule	16 August 1985	Forwards Info Re Control Room Halon Fire Suppression Sys,In Response to 850715 Request.Total Flooding of Halon Sys Will Be Installed in Facility Control Room During Next Refueling Outage,Per 10CFR50.48 Schedule	Safe Shutdown Exemption Request Continuous fire watch
B11646, Forwards Draft Connecticut Yankee Plant Design Change Task Group, Final Rept, Review of Design Change Process, Plant Design Change Evaluations & Screening of Plant Design Changes, Per NRC Request During 850801-02 Audit	9 August 1985	Forwards Draft Connecticut Yankee Plant Design Change Task Group, Final Rept, Review of Design Change Process, Plant Design Change Evaluations & Screening of Plant Design Changes, Per NRC Request During 850801-02 Audit
B11652, Discusses Status of Resolution of Unresolved Item 50-213/85-08-04.Inservice Date of 871201 Planned	3 October 1986	Discusses Status of Resolution of Unresolved Item 50-213/85-08-04.Inservice Date of 871201 Planned
B11655, Advises That Proposed Change to Axial Offsite Limits Will Be Requested for Cycle 14 to Allow 3-loop Operation at All Times During Cycle.Vendor Evaluation Indicated 4-loop Axial Offset Limits Not Always Conservative	16 August 1985	Advises That Proposed Change to Axial Offsite Limits Will Be Requested for Cycle 14 to Allow 3-loop Operation at All Times During Cycle.Vendor Evaluation Indicated 4-loop Axial Offset Limits Not Always Conservative	Unanalyzed Condition
B11656, Forwards Clarification of Proposed Rev to Tech Spec 3.13.C(1) Re Refueling Submitted w/850510 Ltr.Revised Page Clarifies That Fuel Returns to Reactor Core,Not Literally to Bottom of Reactor Pressure Vessel	28 August 1985	Forwards Clarification of Proposed Rev to Tech Spec 3.13.C(1) Re Refueling Submitted w/850510 Ltr.Revised Page Clarifies That Fuel Returns to Reactor Core,Not Literally to Bottom of Reactor Pressure Vessel
B11657, Forwards Tech Spec Page 3-4a Inadvertently Omitted from Attachment 1 of 850709 Submittal Re Proposed Changes to Tech Specs in Response to Generic Ltr 83-43 Covering Reactor Coolant Loops	13 August 1985	Forwards Tech Spec Page 3-4a Inadvertently Omitted from Attachment 1 of 850709 Submittal Re Proposed Changes to Tech Specs in Response to Generic Ltr 83-43 Covering Reactor Coolant Loops
B11659, Discusses Implementation of Mods Providing Equivalent Level of Protection Required by 10CFR50,App R.Non-outage Mods Implemented.Mods in Control Room Will Be Implemented During Next Refueling Outage for Safety Reasons	15 August 1985	Discusses Implementation of Mods Providing Equivalent Level of Protection Required by 10CFR50,App R.Non-outage Mods Implemented.Mods in Control Room Will Be Implemented During Next Refueling Outage for Safety Reasons	Safe Shutdown Fire Barrier Exemption Request Scaffolding
B11660, Provides Informational Update of Analysis of Plant Auxiliary Feedwater Sys.Increased Primary Sys Pressure Predicted for Loss of Main Feedwater Event Has No Unacceptable Safety Impact	28 August 1985	Provides Informational Update of Analysis of Plant Auxiliary Feedwater Sys.Increased Primary Sys Pressure Predicted for Loss of Main Feedwater Event Has No Unacceptable Safety Impact

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