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TEXT-SAFETY REPORT, NUREG REPORTS  and SAFETY EVALUATION REPORT--FACILITY

ASME Section III +  and ASME Section XI +

Boron +, Iodine +, Hydrogen +  and Lead +

10 CFR 20 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 61 +, 10 CFR 73 +, 10 CFR 73.55 +, 10 CFR 73 Appendix B +, 10 CFR 73 Appendix C +, 10 CFR 50.55a +, 10 CFR 50.62#d +, 10 CFR 50.55a#g +, 10 CFR 73.55#f +, 10 CFR 73.55#e +, 10 CFR 73.55#b +, 10 CFR 73.55#a +, 10 CFR 73.55#d +, 10 CFR 73.55#g +, 10 CFR 73.55#h +, 10 CFR 73.55#c +, 10 CFR 73.2#f1 +  and 10 CFR 73.1#a1ii +

00423  +  and 05000423  +

GDC 16 +, GDC 14 +, GDC 18 +, GDC 31 +, GDC 32 +, GDC 51 +, GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +, GDC 4, Environmental and dynamic effects design bases +, GDC 1, Quality standards and records +  and GDC 5, Sharing of structures, systems, and components +

ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +, ML20137L562 +...

ML20093C227 +, B11731, Forwards Addl Info Re Draft Tech Specs,Per 850906 Meeting. Encls Include Responses to Specific Tech Spec & SER Items +, B11720, Forwards Revised FSAR Section 6.2.5.3 Clarifying Discrepancy W/Emergency Operating Procedures Re Actuation of Hydrogen Recombiners,Per 850828 Telcon.Encl Rev Will Be Included in Next Amend to FSAR +, B11572, Forwards Addl Info Re 840515 Response to Core Performance Branch Question 492.5,per NRC 840802 Request.Info Resolves SER Open Item 9 Re Operation of Sys Hardware & Implementation of Loose Parts Detection Program +, B11541, Forwards Response to Request for Addl Info Re Design Basis of Facility Spent Fuel Racks (SER Confirmatory Item 10) +, B11575, Forwards Rev 1 to Radiological Effluent Monitoring & Offsite Dose Calculation Manual. Process Control Program Also Encl.Info Responds to Unit 3 SER Confirmatory Items 59 & 60 +, B11411, Discusses SALP for Facilities.Input to SALP Evaluation Process & Followup to Previous SALP Rept Actions Encl +, B11561, Forwards Reload Safety Analysis in Support of Cycle 7 Reload.Core Reload Will Not Adversely Affect Plant Safety +, A04881, Responds to NRC Re Violations Noted in Insp Rept 50-336/85-17.Corrective Actions:Flow Test Box Modified to Conform W/Requirements of Figure 2605D-1,Sketch 1,including Installation of Test Equipment Valves V-12 & V-13 +, B11553, Forwards Response to SER Confirmatory Item 61 Re Noble Gas Monitors Installed to Meet Requirements of TMI Action Plan Item II.F.1 +, B11489, Forwards Revised Response to Power Sys Branch Mechanical Series SER Item 2.6,including FSAR Commitment That Rocker Arm Lube Oil Reservoir Level Will Be Checked Biweekly on Engines in Standby & Daily on Operating Engines +, B11486, Forwards Small Break Loca/Eccs Performance Analysis W/Axial Shape Index of -0.10. Encl Analysis Amends Loca/Eccs Analysis Provided in Per 10CFR50,App K-II.1.b. Previous Reviews Re Effects of Reloads Remain Valid +, B11422, Forwards Responses to Power Sys Branch 840802 Mechanical Series SER (NUREG-1031) Open Item 2.6,Confirmatory Items 56 & 57 & License Conditions 4,5,6 & 7 +, B11386, Forwards Program to Determine Capability of Millstone 3 Power Plant to Withstand Seismic Excitation.., Per SER (NUREG-1031) Confirmatory Item 1 & Bj Youngblood 840815 Request.Conclusions of Study Listed.W/O Encl +, B11497, Forwards Revs to FSAR Sections 8.2 & 8.3 Re Offsite Power Sys & Emergency Switchgear Bus Protection,Respectively, Closing SER (NUREG-1031),Confirmatory Items 44,45,46 & 50 Per J Knox Request +, B11343, Advises That 840912 Request for Exemption from GDC 4 Should Be Modified,Disregarding All Ref to Considerations for Including P-1 Snubbers,Per 840913 Meeting W/Mechanical Engineering Branch +, B11270, Forwards Second Revised Response to Ser,Item 218 Re Transformers Used as Isolation Devices +, A04078, Forwards Response to Bj Youngblood 840525 Request for Addl Info Re Evacuation During Emergency & Review of FSAR Section 3.9.3.W/one Oversize Drawing.Aperture Card Available in PDR +, B11247, Forwards Summary of 840614 Meeting W/S&W & Structural & Geotechnical Engineering Branch in Response to Structural Audit Confirmatory Items 41 & 15 +, B11228, Forwards Rev 2 to Updated FSAR +, B11223, Forwards Summary Status of Power Sys Branch Electrical Draft SER Open Items Re OL Application Info,Discussed & Resolved at 840514 & 31 Meetings & Responses to Items +, B11180, Forwards Revised Responses to Power Sys Branch Mechanical Series Questions.Responses Consist of marked-up FSAR Pages +, B11037, Forwards Proprietary Response to Question 492.4 Re Measurement of RCS Flow.Response Withheld (Ref 10CFR2.790) +, B11159, Informs That Util Will Submit Revised Emergency Plan by 840630.Plan Will Contain Some Preliminary Elements Owing to Evolution of Plant Procedures.Final Version of Preliminary Elements Will Be Submitted by 850101 +, 05000336/LER-1985-010, :on 850615,loss of Low Temp Overpressure Protection Due to Isolation & Venting of Pressurizer Pressure Transmitters.Caused by Procedure Inadequacy.Porvs Manually Opened & Procedure Revised +, B10839, Final Rept on Significant Deficiency SD-29 Re Cracks in Concrete in Containment Crane Wall Near Embedments.Initially Reported on 821207.Plate Capacity Adequate to Resist Forces from Pipe Rack Trusses.Deficiency Satisfactorily Resolved +  and ML20209D759 +

NUREG-0452 +, NUREG/CR-3756 +, NUREG-1152, Forwards NUREG-1152, Millstone 3 Risk Evaluation Rept. W/O Encl +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, NUREG-1031, Forwards Safety Evaluation Re Emergency Operating Procedures Upgrade Program Per TMI Action Item 1.C.1.Eight Procedures Validated on Simulator & Actions Acceptable +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG/CR-0660, Forwards Sample Ltr to Applicants,Cp Holders & Licensees of LWRs Transmitting NUREG/CR-0660 Enhancement of Onsite Emergency Diesel Generator Reliability +  and NUREG-0577, Forwards Request for Addl Info Re Low Fracture Toughness Since Facility Has Been Classified as Group 1 According to NUREG-0577.Response Should Be Submitted within 30 Days of Receipt of Ltr.Further NRC Evaluation Will Be Required +

Regulatory Guide 1.97 +, Regulatory Guide 1.75 +, Regulatory Guide 1.137 +, Regulatory Guide 1.43 +, Regulatory Guide 1.50 +, Regulatory Guide 1.31 +, Regulatory Guide 1.83 +, Regulatory Guide 1.44 +, Regulatory Guide 1.34 +, Regulatory Guide 1.36 +, Regulatory Guide 1.71 +, Regulatory Guide 1.85 +  and Regulatory Guide 1.37, Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants +

Connecticut +, Maryland +, Washington +, Idaho +, New York +  and Alaska +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Emergency Diesel Generator +, Safety Parameter Display System +, Emergency Core Cooling System +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +, Extraction steam +  and Turbine Gland Sealing System +

Hot Short +, Safe Shutdown +, Grab sample +, Offsite Dose Calculation Manual +, Tornado Missile +, Safe Shutdown Earthquake +, Operating Basis Earthquake +, Nondestructive Examination +, Emergency Lighting +, Shift Technical Advisor +, Process Control Program +, Stress corrosion cracking +, Loss of Offsite Power +, Eddy Current Testing +, Safeguards Contingency Plan +, Earthquake +, Turbine Missile +, Offsite Circuit +, Failure to Scram +, Negative Flux Rate Trip +  and Spent fuel rack +

WCAP-9401 +, WCAP-8691 +, WCAP-9402 +  and WCAP-10298 +

WCAP-9401 +, WCAP-8691 +, WCAP-9402 +  and WCAP-10298 +