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List of results

• ML20245G873  + (Provides Final Response to NRC Bulletin 88-010, Non-Conforming Molded-Case Circuit Breakers. Review of Purchasing & Audit Records for Eight Remaining Circuit Breakers Verified Traceability to Original Mfg)
• GO2-90-162, Provides Final Response to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow  + (Provides Final Response to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow)
• JSP-005-94, Provides Final Response to NRC Bulletin 93-003, Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in Bwrs  + (Provides Final Response to NRC Bulletin 93-003, Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in Bwrs)
• RBG-44320, Provides Final Response to NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs. Licensee Has Completed Actions Requested by Subj Bulletin  + (Provides Final Response to NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs. Licensee Has Completed Actions Requested by Subj Bulletin)
• ML20235J165  + (Provides Final Response to NRC Bulletin 88-001, Defects in Westinhouse Circuit Breakers. Alignment Check Specified in 871201 Submittal Satisfactorily Performed During Installation of Replacement Pole Shaft in Breakers)
• ML20196H446  + (Provides Final Response to NRC GL 96-01, Testing of Safety-Related Logic Circuits)
• PY-CEI-NRR-2423, Provides Final Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Npps. Remediation of Meteorological Monitoring Sys Has Been Completed & Ppnp Facility Is Now Y2K Ready  + (Provides Final Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Npps. Remediation of Meteorological Monitoring Sys Has Been Completed & Ppnp Facility Is Now Y2K Ready)
• ML20210S607  + (Provides Final Response to NRC RAI Re GL 98-01, Y2K Readiness of Computer Systems at Npps)
• ML20056A954  + (Provides Final Response to NUREG-0737,Item II.D.1, Performance Testing of Safety Relief Valves. Util Will Change Seal Configuration for Existing Valves to Seal on Steam Medium & Install Continuous Drain for Loop Piping)
• ML20055F830  + (Provides Final Response to Noncomformance 3 Resulting from Insp Rept 99900277/90-01,per Initial Response on 900510. Instrument Calibr in 10 Teraohm Range & Found to Be Accurate within Limits Established by QA Sys)
• B17731, Provides Final Response to RAI Concerning Significant Items That Need to Be Accomplished Prior to Restart.Unit 2 Is Currently in Mode 4.Items Will Be Completed by 990414  + (Provides Final Response to RAI Concerning Significant Items That Need to Be Accomplished Prior to Restart.Unit 2 Is Currently in Mode 4.Items Will Be Completed by 990414)
• B17119, Provides Final Response to RAI Raised at Public Meeting on 980219,w/NRC & NNECO Pertaining to Recirculation Spray Sys at Millstone Nuclear Power Station,Unit 3.NNECO Provided Response to NRC Questions 1,2, & 4.Question no.3 Attached  + (Provides Final Response to RAI Raised at Public Meeting on 980219,w/NRC & NNECO Pertaining to Recirculation Spray Sys at Millstone Nuclear Power Station,Unit 3.NNECO Provided Response to NRC Questions 1,2, & 4.Question no.3 Attached)
• CY-98-051, Provides Final Response to RAI on Beyond Design Basis Event of Loss of Water from Spent Fuel Pool at Plant.Changes to Licensee 980318 Submittal Are Shown by Marking in Margin  + (Provides Final Response to RAI on Beyond Design Basis Event of Loss of Water from Spent Fuel Pool at Plant.Changes to Licensee 980318 Submittal Are Shown by Marking in Margin)
• ML20012E653  + (Provides Final Response to Reporting Requirement 2 of NRC Bulletin 88-008, Thermal Stresses in Piping Connected to RCS, for Unit.Nde Requirements of Action 2 Not Considered Applicable to Unit)
• RBG-40657, Provides Final Response to Suppl 1 of NRC Bulletin 93-002, Debris Plugging of Emergency Core Cooling Suction Strainers  + (Provides Final Response to Suppl 1 of NRC Bulletin 93-002, Debris Plugging of Emergency Core Cooling Suction Strainers)
• ML20100J089  + (Provides Final Responses to Generic Ltr 81-14, Seismic Qualification of Auxiliary Feedwater Sys. Support Straps on Battery Racks Replaced as Scheduled in)
• DCL-85-050, Provides Final Responses to IE Bulletins 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts & 79-14, Seismic Analysis for As-Built Safety- Related Piping Sys  + (Provides Final Responses to IE Bulletins 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts & 79-14, Seismic Analysis for As-Built Safety- Related Piping Sys)
• ML20217C256  + (Provides Final Results of Analysis of Suppression Pool Temp & Pressure for Limiting LOCA in Regard to Low Pressure ECCS Pump Npsh,Per License Condition Stated)
• ML20101R570  + (Provides Final Results of Facility Core Shroud Exams)
• ML20084N293  + (Provides Final Results of Quad Cities Nuclear Station Unit 2 Core Shroud Exams,Per GL 94-03)
• ML20237A963  + (Provides Final Results of Revised Calculations Addressing Thermo-Lag Fire Barrier Seismic Capability)
• ML20154A986  + (Provides Final Results of Revised Calculations Which Address Thermo-Lag Fire Barrier Seismic Capability,As Previously Committed to in Licensee to NRC)
• ML20209G371  + (Provides Final Root Cause Evaluation Re GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 1)
• 3F1097-05, Provides Final Status Rept of GL 96-06, Assurance of Equipment Operability & Containment Integrity During DBA Conditions, Issues for Plant & Necessary Actions Necessary to Resolve Safety Concerns  + (Provides Final Status Rept of GL 96-06, Assurance of Equipment Operability & Containment Integrity During DBA Conditions, Issues for Plant & Necessary Actions Necessary to Resolve Safety Concerns)
• ML20079J120  + (Provides Final Status Rept of IE Bulletin 79-14, Seismic Analysis for As-Built Safety-Related Piping Sys. Complete & Final Listings of Portions of Sys Failing to Meet FSAR Requirements Under Nutech Responsibility Encl)

• GO2-94-185, Provides Final Status Rept of Revised WNP-2 Corrective Action Program  + (Provides Final Status Rept of Revised WNP-2 Corrective Action Program)

• ML20212D597  + (Provides Final Status Rept on Electrical Calculations for Restart at Facility.All Required Calculations Performed & All Conditions Adverse to Quality Identified for Corrective Action)
• ML20059A410  + (Provides Final Status of Activities Required by NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification)
• ML20234F292  + (Provides Final Status of Investigation of Unstable Condensate Storage Tank Level Indication Experienced During Cycle 6 Startup Tests.Caused by Pump Suction Flow Across Level Transmitter Instrument Taps)
• ML20149H184  + (Provides Final Summary Rept Consisting of Core Shroud Insp Results,As Requested by Reporting Requirement 3 of GL 94-03. Overall Results of Insp Revealed Min Amount of Flaws)
• ML20031B912  + (Provides Final Test Results Demonstrating Operational Adequacy of Safety Relief Valve,In Response to NUREG-0737, Item II.D.1)
• ML20011A263  + (Provides Final Test Results Demonstrating Operational Adequacy of Safety Relief Valves in Response to NUREG-0737 Item II.D.1)
• ML20011A273  + (Provides Final Test Results Re Operational Adequacy of Safety Relief Valves,Per TMI Action Plan Item II.D.1)
• AECM-81-377, Provides Final Test Results Which Demonstrate Operational Adequacy of Safety Relief Valves for Piping & Supports.Final Test Results Are Contained in NEDE-24988-P Submitted by BWR Owners Group on 810925  + (Provides Final Test Results Which Demonstrate Operational Adequacy of Safety Relief Valves for Piping & Supports.Final Test Results Are Contained in NEDE-24988-P Submitted by BWR Owners Group on 810925)
• ML20031E362  + (Provides Final Test Results Which Demonstrate Operational Adequacy of Safety & Relief Valves,In Response to NUREG-0737,Item II.D.1)
• ML20032C240  + (Provides Final Test Results Which Demonstrate Operational Adequacy of Safety/Relief Valve in Response to NUREG-0737 Item II.D.1 & Adequacy of Safety/Relief Discharge Piping & Supports.Final Results Contained in NEDE-24988-P)
• ML18030A351  + (Provides Final Test Results Which Demonstrate Operational Adequacy of Safety Relief Valves.Submittal of NEDE-24988-P Satisfies 811001 & 820101 Submittal Requirements of NUREG- 0737,Item II.D.1)
• ML20031C516  + (Provides Final Test Results Which Demonstrate Operational Adequacy of Safety Relief Valves for Discharge Piping & Supports.Test Results Are Contained in NEDE-24988-P Which Will Be Submitted by BWR Owners Group Approx 811001)
• GO2-81-421, Provides Final Test Results to Demonstrate Operational Adequacy of Safety Relief Valve for Facility,In Response to NUREG-0737,Item II.D.1.Submittal of NEDE-24988-P & Ltr Completes Item  + (Provides Final Test Results to Demonstrate Operational Adequacy of Safety Relief Valve for Facility,In Response to NUREG-0737,Item II.D.1.Submittal of NEDE-24988-P & Ltr Completes Item)
• B14428, Provides Final Test Results,Contained in Encl WCAP-13630, Evaluation of Upper Shelf Energy Behavior of Two Nozzle Shell Plates in Connecticut Yankee Reactor Vessel, Per Suppl 1 to GL 92-01  + (Provides Final Test Results,Contained in Encl WCAP-13630, Evaluation of Upper Shelf Energy Behavior of Two Nozzle Shell Plates in Connecticut Yankee Reactor Vessel, Per Suppl 1 to GL 92-01)
• ML20039A184  + (Provides Final Test Results,Demonstrating Operational Adequacy of Safety Relief Valves,Per NUREG-0737 Item II.D.1. Adequacy of Discharge Piping & Supports Demonstrated in NEDE-24988-P)
• PY-CEI-NRR-0355, Provides Final Update of Equipment Qualification Issues for Closing Out Outstanding Issue 4.All Equipment within Scope of 10CFR50.49 Qualified & All Active safety-related Pumps & Valves Qualified for Operability.Test List Encl  + (Provides Final Update of Equipment Qualification Issues for Closing Out Outstanding Issue 4.All Equipment within Scope of 10CFR50.49 Qualified & All Active safety-related Pumps & Valves Qualified for Operability.Test List Encl)
• ML20078A017  + (Provides Final Update on Status of Plant Procedures Upgrade Project.Informs That Project Completed & Remains on Schedule for Dec 1995 Completion)
• ML20086C485  + (Provides Final Weld Design Package,In Response to Commitments Made Re Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping)
• ML19257C986  + (Provides Final Work Assignments for Containment Leakage Testing,Control of Heavy Loads,Low Fracture Toughness,Bwr Feedwater Nozzle Cracking & Containment Purge)
• ML20055H480  + (Provides Financial Assurance Documentation for Decommissioning of Triga Reactor.Estimate for Decommissioning Based on Info Obtained from NUREG/CR-1756)
• ML20115J182  + (Provides Financial Info as Amend to Paragraph (F) of General Info Submitted in 831109 License Application & Subsequent Submittals.Funding Approval for Major Changes in Physical Plant Is Responsibility of Board of Regents)
• ML19270H252  + (Provides Financial Info to Demonstrate That Vallecitos Nuclear Ctr Has Resources Necessary to Operate & Shut Down Decommissioning Facility)
• ML17156A632  + (Provides Finding of No Adverse Effect in Response to 870320 Submittal Re Archeological Sites on Plant Property.Util Should Submit Request for Amends to Environ Protection Plans in Licenses NPF-14 & NPF-22)
• ML20096C032  + (Provides Findings & Positions Re Investigation of 840623 Failure of Six Control Rods to Automatically Insert Upon Scram.Summary of Work on Four CRDs & Description of Tests Encl.Corrective Actions Listed)
• ML20147C023  + (Provides Findings Re Proposed Lic ISNM-1692 for Subj Facil to Import Plutonium from Japan to Getr Site in Ca.Proposed Action Will Not Impact on Environ or General Public)