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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.

List of results

• ML20215E777  + (Safety Evaluation Re Inservice Insp Program & Requests for Relief from Certain Inservice Insp Requirements)
• ML20210S273  + (Safety Evaluation Re Inservice Insp Program & Requests for Relief)
• ML20044B757  + (Safety Evaluation Re Inservice Insp Program Relief Request for Plants)
• ML17229A126  + (Safety Evaluation Re Inservice Insp Request for Relief for Florida Power & Light Co,St Lucie Plant,Units 1 & 2)
• ML19312C422  + (Safety Evaluation Re Inservice Insp of Steam Generator Tube Degradation.No Significant Degradation Expected Before Next Insp)
• ML20041C215  + (Safety Evaluation Re Inservice Test Program & Granting of Relief from ASME Code Section XI Inservice Testing Requirements)
• ML18153C352  + (Safety Evaluation Re Inservice Testing Program & Requests for Relief.Requests for Relief Acceptable for Implementation Provided Omissions & Inconsistencies Identified in App C of Technical Evaluation Rept Corrected)
• ML17306B076  + (Safety Evaluation Re Inservice Testing Program Requests for Relief Concerning Safety Injection Check Valves)
• ML20059C405  + (Safety Evaluation Re Inservice Testing Program Relief Requests GR-7 & RCIC-6 for Plant.Proposed Alternative to OM-1 Safety & Valve Relief Valve Requirements Authorized Based on Alternative Providing Acceptable Level of Quality)
• ML20035G513  + (Safety Evaluation Re Inservice Testing Program & Request for Relief.Relief Requests Will Provide Reasonable Assurance of Operational Readiness of Pumps & Valves to Perform safety-related Functions)
• ML20057F412  + (Safety Evaluation Re Inservice Testing Program Requests for Relief.Alternatives Authorized Per 10CFR50.55a(a)(3) or Relief Granted Per 10CFR50.55a(f)(6)(i))
• ML20059L921  + (Safety Evaluation Re Inservice Testing Program & Requests for Relief from Requirements Deemed Impractical to Perform at Facilities)
• ML20045E046  + (Safety Evaluation Re Inservice Testing Program Requests for Relief.Relief Granted)
• ML16141A907  + (Safety Evaluation Re Inservice Testing Program Requests for Relief.Interim Relief Granted Per 10CFR50.55a(f)(6)(i) in Paragraph 3.5)
• ML20246F467  + (Safety Evaluation Re Inservice Testing Program & Requests for Relief Re ASME Class 1,2 & 3 Pumps & Valves.Program Acceptable)
• ML20235B638  + (Safety Evaluation Re Inservice Testing Program & Requests for Relief from ASME Code,Section Xi.Program for Pumps & Valves & Request for Relief Acceptable.Relief Requests May Not Be Implemented W/O Prior NRC Approval)
• ML17227A710  + (Safety Evaluation Re Inservice Testing Program & Request for Relief.Summary of Relief Requests Encl)
• ML20237H597  + (Safety Evaluation Re Inservice Testing Program & Requests for Relief.Program Acceptable for Implementation)
• ML20056G430  + (Safety Evaluation Re Inservice Testing Program Requests for Relief.Licensee Made Changes to Subj Program to Include Exercising & fail-safe Testing of Auxiliary Feedwater Valves AF-6451 & AF-6452,in Response to TER Anomaly 8)
• ML20151X065  + (Safety Evaluation Re Inservice Testing Program Relief Request VR-63 for Plant)
• ML20151X012  + (Safety Evaluation Re Inservice Testing Program & Requests for Relief)
• ML17056B079  + (Safety Evaluation Re Inservice Testing Program & Requests for Relief)
• ML17056C027  + (Safety Evaluation Re Inservice Testing Program & Requests for Relief)
• ML20083E905  + (Safety Evaluation Re Inservice Testing Program Relief Request)
• ML20029A716  + (Safety Evaluation Re Inservice Testing Program Relief Request for Plant)

• ML20035E482  + (Safety Evaluation Re Inservice Testing Program Relief Requests)

• ML20246A074  + (Safety Evaluation Re Inservice Testing Program for Pumps & Valves)
• ML20057C040  + (Safety Evaluation Re Inservice Testting Program Requests for Relief)
• ML20127C796  + (Safety Evaluation Re Insp & Repair of RCS Piping.Plant Can Be Safely Returned to Operation in Present Configuration for Duration of Cycle 7)
• ML20214A557  + (Safety Evaluation Re Insp & Repair of Reactor Coolant Piping Sys & Supporting Return to Operation for Next Operating Cycle)
• ML20214Q385  + (Safety Evaluation Re Insp & Repair of Reactor Coolant Piping Sys)
• ML20198P673  + (Safety Evaluation Re Insp & Repairs of Isolation Condenser Sys Piping.Piping Inspected & Repaired in Accordance W/Nrc Guidelines.Facility Can Be Safely Returned to Operation Until Next Refueling Outage)
• ML17195A740  + (Safety Evaluation Re Insp & Repairs of RCS Piping)
• ML20202H263  + (Safety Evaluation Re Insp & Repairs of Reactor Coolant Piping Sys Welds Susceptible to IGSCC During 1985 Refueling Outage.Insp & Repairs Satisfactory.Facility Can Be Safely Returned to Power & Operated for 18-month Fuel Cycle)
• ML20238A680  + (Safety Evaluation Re Insps & Repairs of Igscc.Plant Can Be Safely Operated for Another 18-month Fuel Cycle in Present Configuration)
• ML20236J815  + (Safety Evaluation Re Insps for & Repairs of IGSCC During Reload 7/Cycle 8 Refueling Outage.Facility Can Be Safely Operated for One 18-month Fuel Cycle in Present Configuration)
• ML20205H135  + (Safety Evaluation Re Insps for & Repairs of Igscc.Facility Can Be Safely Operated for One 18-month Fuel Cycle in Present Configuration)
• ML20235A733  + (Safety Evaluation Re Installation of Alternate Rod Injection (ARI) Sys & Adequacy of Plant Reactor Coolant Recirculating Pump Trip (RPT) Sys,In Compliance W/Atws Rule 10CFR50.62. ARI & RPT Acceptable)
• ML19347C550  + (Safety Evaluation Re Installation of Steam Generator Upper Insp Ports During Second Refueling Outage.Licensee Should Commit to Installation During Third Refueling Outage)
• ML17255A270  + (Safety Evaluation Re Integrated Plant SAR Section 4.17.1 Concerning Containment Liner Insulation.Liner Will Retain leak-tight Integrity During Postulated Loadings)
• ML20083C868  + (Safety Evaluation Re Intergranular Stress Corrosion Cracking Insp.Plant Can Be Safely Returned to Power in Present Configuration for One 5-month Period)
• ML20087F374  + (Safety Evaluation Re Intergranular Stress Corrosion Cracking Insp & Repair.Plans for Insp & Mod of Recirculation & Other RCPB Piping Sys Should Be Submitted for Review 3 Months Before Refueling Outage)
• ML20081A604  + (Safety Evaluation Re Intergranular Stress Corrosion Cracking.Insp & Mod Plans Must Be Submitted to NRC at Least 3 Months Prior to Start of Next Refueling Outage)
• ML19309B847  + (Safety Evaluation Re Interim Actions Taken to Eliminate Feedwater Piping Cracks,Performed in Response to IE Bulletin 79-13.Repair Method,Nondestructive & Visual Insp & Inherent Toughness of Piping Matls Are Adequate)
• ML20214Q869  + (Safety Evaluation Re Interim Operation W/O Bypassed & Inoperable Status Panel)
• ML20004D196  + (Safety Evaluation Re Isolation Condenser Steam Line Water Hammer & Pipe Anchor Safety Factor.Two Design Areas Require Factor of Safety of at Least 4 for Expansion Anchor Bolts Under All Design Conditions)
• ML20128Q651  + (Safety Evaluation Re Item 1.1 of Generic Ltr 83-28, Post-Trip Review. Review Program & Procedures Acceptable)
• ML15238B289  + (Safety Evaluation Re Item II.K.2.19 Benchmark Analysis of Sequential Auxiliary Feedwater Flow for B&W Reactor Plants. Intent of Action Item II.K.2.19 Accomplished & Results Provided by CRAFT-2 Similar to TRAP-2 Program)
• ML20214S873  + (Safety Evaluation Re LER 269/86-006 Concerning Moderator Temp Coefficient.Concurs W/Licensee Assessment,Actions Taken or to Be Taken.Four Impacted FSAR Events All Remained within Respective Safety Criteria)
• ML17187B137  + (Safety Evaluation Re LPCI & Spray Pump Casing Fracture Toughness,Commonwealth Edison Co,Dresden Nuclear Power Station,Units 2 & 3)
• ML17221A505  + (Safety Evaluation Re Large Break LOCA ECCS Reanalysis. Concludes That Facility in Compliance W/Criteria of 10CFR50.46 & App K to 10CFR50 & That Large Break LOCA Reanalysis Acceptable)