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A08900, Responds to Expressing NRC Views on Access to Util Internal or third-party Assessment Repts.Believes Internal Analysis to Support Amend of One of Util NRC OLs to Authorize Higher Power Level Is within NRC Purview & Access11 September 1990Responds to Expressing NRC Views on Access to Util Internal or third-party Assessment Repts.Believes Internal Analysis to Support Amend of One of Util NRC OLs to Authorize Higher Power Level Is within NRC Purview & Access
ML20064A80711 September 1990Forwards Core Operating Limits Rept for Four & Three Loop Operation,Per Tech Spec 6.9.1.6.d
B13628, Forwards Correction to Error Discovered in Util 900727 Response to Notice of Violation from Insp Rept 50-336/90-09. Statement Corrected to Read That Contract Personnel That Have long-term Assignments,Certified as Testing Personnel7 September 1990Forwards Correction to Error Discovered in Util 900727 Response to Notice of Violation from Insp Rept 50-336/90-09. Statement Corrected to Read That Contract Personnel That Have long-term Assignments,Certified as Testing Personnel
B13624, Forwards Addl Info Re Relief Request from ASME Code Section XI Requirements for Temporary Repair to Piping Adjacent to Valve 2-SW-97A,per 900817 Telcon5 September 1990Forwards Addl Info Re Relief Request from ASME Code Section XI Requirements for Temporary Repair to Piping Adjacent to Valve 2-SW-97A,per 900817 TelconSafe Shutdown
A08977, Advises of Commitment to Install Hardened Wetwell Vent at Facility,In Response to NRC .Util Will Be Proceeding W/Initial Design & Engineering of Hardened Vent, to Support Installation During 1993 Refueling Outage4 September 1990Advises of Commitment to Install Hardened Wetwell Vent at Facility,In Response to NRC .Util Will Be Proceeding W/Initial Design & Engineering of Hardened Vent, to Support Installation During 1993 Refueling OutageHardened vent
B13626, Informs That Info Provided in Re safety-related Equipment Classification Programs Also Applicable for Unit 3 of Facility31 August 1990Informs That Info Provided in Re safety-related Equipment Classification Programs Also Applicable for Unit 3 of Facility
B13596, Forwards Millstone Unit 3 Individual Plant Exam for Severe Accident Vulnerabilities, Per Generic Ltr 88-20.Rept Identified That No Major Severe Accident Vulnerabilities Requiring Corrective Action Needed31 August 1990Forwards Millstone Unit 3 Individual Plant Exam for Severe Accident Vulnerabilities, Per Generic Ltr 88-20.Rept Identified That No Major Severe Accident Vulnerabilities Requiring Corrective Action NeededInternal Flooding
Probabilistic Risk Assessment
B13622, Forwards Crdr Human Engineering Discrepancy Info for Plant30 August 1990Forwards Crdr Human Engineering Discrepancy Info for Plant
B13618, Forwards Addl Info on Util 900815 Relief Request from ASME Code Section XI Requirements,Per 10CFR50.55a(g)(6)(i),for Repairs to Pipe 3SWP-006-050-0324 August 1990Forwards Addl Info on Util 900815 Relief Request from ASME Code Section XI Requirements,Per 10CFR50.55a(g)(6)(i),for Repairs to Pipe 3SWP-006-050-03Safe Shutdown
ML20059C20623 August 1990Forwards Vols 1 & 2 to Semiannual Radioactive Effluents Release Rept Jan-June 1990, Per 10CFR50.36a.Rept Includes Summary of Quantities of Solid Radwaste & Liquid & Gaseous Effluents
A08918, Responds to Notice of Violation & Proposed Imposition of Civil Penalty Re Insp Rept 50-245/90-08.Mitigation of Civil Penalty Requested.Corrective Action:List of Procedural Changes Provided22 August 1990Responds to Notice of Violation & Proposed Imposition of Civil Penalty Re Insp Rept 50-245/90-08.Mitigation of Civil Penalty Requested.Corrective Action:List of Procedural Changes Provided
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 Issues22 August 1990Requests 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 Amend20 August 1990Requests 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 199016 August 1990Forwards, Semiannual Radioactive Effluents Release Rept for Jan-June 1990
B13610, Requests Relief from ASME Boiler & Pressure Vessel Code Section XI Requirements Re Mods to Pipe 3SWP-006-050-03. Results of Insps & Required Repairs Will Determine Schedule for Future Insps15 August 1990Requests Relief from ASME Boiler & Pressure Vessel Code Section XI Requirements Re Mods to Pipe 3SWP-006-050-03. Results of Insps & Required Repairs Will Determine Schedule for Future Insps
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 Changes14 August 1990Submits 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
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-139414 August 1990Notifies NRC That Utils Volunteer to Participate in Emergency Response Data Sys Project for All Four Nuclear Units,Per Generic Ltr 89-15 & NUREG-1394
B13607, Requests Relief from ASME Code Section XI to Reflect Mod to Piping Adjacent to Valve 2-SW-97A,in Response to Generic Ltr 90-0510 August 1990Requests Relief from ASME Code Section XI to Reflect Mod to Piping Adjacent to Valve 2-SW-97A,in Response to Generic Ltr 90-05
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 Statement10 August 1990Discusses 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
A08845, Responds to NRC Backfit Analyses of Hardened Wetwell Vent, Contained in .Benefit of Installing Hardened Wetwell Vent to Satisfy Basic Design Objective of Preventing core-melt Event Not Sufficient for Immediate Decision8 August 1990Responds to NRC Backfit Analyses of Hardened Wetwell Vent, Contained in .Benefit of Installing Hardened Wetwell Vent to Satisfy Basic Design Objective of Preventing core-melt Event Not Sufficient for Immediate DecisionBackfit
ML20058M8327 August 1990Discusses Spent Fuel Racks Poison Surveillance Coupon Boraflex Degradation.Visual Exam of Remaining Surveillance Coupons Revealed Similar Situation Existed in All Coupon Samples
ML20058N2187 August 1990Notification of Change in Senior Operator Status.Util Determined That Need to Maintain Senior OL of LS Allen No Longer Exists.Determination Effective 900719
B13603, Withdraws 900731 Request for Temporary Waiver of Compliance W/Tech Spec 3.7.1.2 Re Inoperability of Auxiliary Feedwater Pumps2 August 1990Withdraws 900731 Request for Temporary Waiver of Compliance W/Tech Spec 3.7.1.2 Re Inoperability of Auxiliary Feedwater Pumps
B13590, Responds to NRC 900718 Request for Addl Info Re Util 900418 Request for Schedular Exemption from 10CFR50,App E,Section IV.F.3 to Allow Dec 1990 Full Participation Exercise to Be Exchanged W/Oct 1991 Partial Participation Exercise1 August 1990Responds to NRC 900718 Request for Addl Info Re Util 900418 Request for Schedular Exemption from 10CFR50,App E,Section IV.F.3 to Allow Dec 1990 Full Participation Exercise to Be Exchanged W/Oct 1991 Partial Participation Exercise
A08881, Responds to NRC Re Violations Noted in Insp Rept 50-423/90-08.Corrective Action:Operators Directly Involved W/Event Removed from Licensed Duties & Counseled by Operations Manager on Causes of Event31 July 1990Responds to NRC Re Violations Noted in Insp Rept 50-423/90-08.Corrective Action:Operators Directly Involved W/Event Removed from Licensed Duties & Counseled by Operations Manager on Causes of Event
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 Inoperable31 July 1990Requests 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
B13594, Forwards Rev 13 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21(b) & 2.790(a))30 July 1990Forwards Rev 13 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21(b) & 2.790(a))
ML20055J46227 July 1990Advises That Need to Maintain OL or Senior OL for Listed Individuals No Longer Exists,Effective 900701
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 Sys26 July 1990Provides 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
A08565, Responds to NRC 900302 Request for Addl Info Re LPCI Swing Bus Transfer Design & Single Failure Vulnerabilities26 July 1990Responds to NRC 900302 Request for Addl Info Re LPCI Swing Bus Transfer Design & Single Failure Vulnerabilities
B13592, Requests Extension to Respond to NRC Backfit Analyses of Hardened Wetwell Vent24 July 1990Requests Extension to Respond to NRC Backfit Analyses of Hardened Wetwell VentBackfit
ML20063P97923 July 1990Notification of Change in SL Jackson Status Effective 900701,due to Permanent Reassignment within Util
B13563, Discusses Util Comprehensive Review of Options Re Degraded Grid Undervoltage Protection.Confirms Previous Conclusion That Splitting Loss of Normal Power Logic Would Have Overall Adverse Impact on Plant Safety20 July 1990Discusses Util Comprehensive Review of Options Re Degraded Grid Undervoltage Protection.Confirms Previous Conclusion That Splitting Loss of Normal Power Logic Would Have Overall Adverse Impact on Plant Safety
B13566, Advises That Util Has Reasonable Assurance That Safety Relief Valves Operable & Will Perform as Expected Until Next Outage20 July 1990Advises That Util Has Reasonable Assurance That Safety Relief Valves Operable & Will Perform as Expected Until Next Outage
B13571, Clarifies 900625 Tech Spec Change Request Re Limit of 160 Failed Fuel Rods for Cycle 16 Operation19 July 1990Clarifies 900625 Tech Spec Change Request Re Limit of 160 Failed Fuel Rods for Cycle 16 Operation
ML20055G53318 July 1990Forwards Decommissioning Financial Assurance Certification Rept
A08822, Submits Addl Info Requested Re Util Response to Generic Ltr 88-11, Radiation Embrittlement of Reactor Vessel Matls. Charpy Impact Use Values for Welds Provided in Evaluation of Irradiated Capsule W-9718 July 1990Submits Addl Info Requested Re Util Response to Generic Ltr 88-11, Radiation Embrittlement of Reactor Vessel Matls. Charpy Impact Use Values for Welds Provided in Evaluation of Irradiated Capsule W-97
B13588, Corrects 900703 Submittal of Results of Second in-cycle Insp of Steam Generators.All Tubes W/Cracks Stacked & Plugged18 July 1990Corrects 900703 Submittal of Results of Second in-cycle Insp of Steam Generators.All Tubes W/Cracks Stacked & Plugged
B13569, Forwards, Haddam Neck Plant Decommissioning Financial Assurance Certification Rept18 July 1990Forwards, Haddam Neck Plant Decommissioning Financial Assurance Certification Rept
B13587, Requests Temporary Waiver of Compliance from Tech Spec 3.5.F.2 Re Emergency Diesel Generator (EDG) Limiting Condition for Operation.Waiver Would Extend Available Time to Repair Damaged Electrical Components16 July 1990Requests Temporary Waiver of Compliance from Tech Spec 3.5.F.2 Re Emergency Diesel Generator (EDG) Limiting Condition for Operation.Waiver Would Extend Available Time to Repair Damaged Electrical Components
ML20055E6796 July 1990Responds 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
ML20055D3463 July 1990Responds 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 FacilityOperability Determination
ML20055D71929 June 1990Amends 900604 Rev 13 to QA Program
ML20055D34829 June 1990Forwards Addl Info Re Facility Crdr & Isap,Including Justification for Human Engineering Discrepancies Dispositioned for No Corrective Action
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 Indication29 June 1990Provides 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
B13545, Forwards Rev 3 to Updated FSAR for Millstone Unit 329 June 1990Forwards Rev 3 to Updated FSAR for Millstone Unit 3
B13550, Responds to Generic Ltr 90-04, Request for Info on Status of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Implementation & Completion Tables for staff-imposed Requirements Encl27 June 1990Responds to Generic Ltr 90-04, Request for Info on Status of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Implementation & Completion Tables for staff-imposed Requirements Encl
B13499, Forwards Corrected Tech Specs Page 3/4 9-1 for Incorporation Into Proposed Amend 36 to License DPR-21 Re Auxiliary Electrical Sys26 June 1990Forwards Corrected Tech Specs Page 3/4 9-1 for Incorporation Into Proposed Amend 36 to License DPR-21 Re Auxiliary Electrical Sys
ML20043F87211 June 1990Corrects Name of Vendor Supplying Replacement Plug Valves, Per Util 900511 Ltr.Replacement Bolts,Not Valves,Purchased from Cardinal Industrial Products Corp
ML20043H0168 June 1990Requests Exemption from App J to 10CFR50 for 12 Valves in Reactor Bldg Closed Cooling Water Sys.Valves Not within Definition of Containment Isolation Valves in App J & Not Required to Be TestedExemption Request
Backfit
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