RA-15-0009, Supplement to Application for Order Approving Transfer of Control of License and for Conforming License Amendment Pursuant to 10 CFR 50.80 and 10 CFR 50.90
DCL-12-069, Diablo Canyon, Units 1 and 2 - Process Protection System Replacement Interface Requirements Specification (Irs), Revision 6, Attachment 3
BYRON 2010-0041, Steam Generator - Inservice Inspection Summary Report for Refueling Outage 15
L-PI-08-062, Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimates
Press Release-01-066, NRC Seeks Comments on Proposed Agenda for Annual Nuclear Safety Research Conference in October
IA-84-564, Draft Commission Paper Recommending Approval of Final Rulemaking to Revise & Update Regulations & License Fee Schedules for Facilities & Matls Applications,Permits, Licenses & Insps
1CAN088907, Requests Relief from Impractical ASME Code Section XI Requirement to Perform 57 Exams of Partially Accessible Welds from First Inservice Insp Interval
RA-98-0153, Transmits Description of Rev 0 to Physical Security & Safeguards Contingency Plan, Which Contains Plant Industrial Security Plan & Safeguards Contingency Plan,Per 10CFR72.44(e)
NG-98-0531, Forwards Comments on NRC Draft SE for DAEC Conversion to Improved TS Based Upon NUREG-1433.Draft SE Contains Util Markups & Typed Inserts
NSD-NRC-97-4935, Forwards Documents Which Summarize Westinghouse Response to Issues in NRC Re AP600 Structural Module
NMP1L3518, Proposed Alternative to Utilize Specific Provisions of Code Case N-716-3, Alternative Classification and Examination Requirements Section XI, Division 1
LD-92-089, Forward Draft Rev of Pilot ITAAC for Sys 80+ Std Design,In Response to NRC 920521 Comments on 920430 Submittal.Revs Account for Comments Provided by NUMARC & Reflect Comments Obtained in NUMARC 920716 Meeting
05000334/LER-1998-021, :on 980324,discovered Gas Voids in Low Head Safety Injection Discharge Piping to Suction Piping of Charging/Head Safety Injection Pumps.Cause of Event Not Established.Procedures Will Be Revised
2CAN088915, Requests Relief from ASME Section XI Code Requirements Limiting Exams
RBG-30603, Radiological Environ Operating Rept for River Bend Operating Station for 1988
B17804, Monthly Operating Rept for May 1999 for Mnps,Unit 2.With
05000265/LER-1985-008-01, :on 850401 Visual Insp Revealed Recirculation Weld Area W/Water Seeping from Small Crack & Circumferential & Axial Indications in Heat Affected Zones.Caused by Igscc. Indications Repaired by Applying Weld Overlay
LD-92-043, Forwards Response to Remaining Outstanding Request for Addl Info (RAI) 230.1 & Revs to Responses for RAIs 220.6 & 220.7, Providing Figure 3.7-2 & Expanding Description of How Average Power Spectral Density Calculated,Respectively
JAFP-84-0338, Radiological Environ Surveillance Rept,1983
05000265/LER-1978-031-03, /03L-0:on 780910,during Testing,Msiv 2-203-3c Failed to Give Half Scram in Reactor Protection Sys Channel B.Caused by Equipment Failure.Msiv Inspected & Adjustor Arm Adjusted
NLS8400127, Forwards Addl Info Resolving Open Items of SER Re Environ Qualification of safety-related Electrical Equipment. Proposed Resolution of Deficiencies Discussed During 840329 Meeting W/Nrc.Issuance of Sser Requested
W3P81-2545, Forwards Public Version of Response to NRC Questions Re Evacuation Time Estimates,Including Info Concerning Use of Speed/Density Relationships Used in Evacuation Model. Evacuation Time Estimate Schematic & Flow Charts Encl
05000245/LER-1979-033-03, /03L-0:on 791113,while Performing Routine Surveillance,Main Steam Line P Switch Failed to Trip at Proper Setpoint.Caused by Setpoint Drift.Switch Adjusted & Satisfactorily Tested
RS-18-098, Seismic Probabilistic Risk Assessment Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from .
NSD-NRC-98-5640, Transmits Rev 4 of Section 3.0, Non-Sys Based Design Descriptions & ITAAC & Section 5.0, Site Parameters of AP600 Certified Design Matl.Changes Made as Result of W Responses to NRC Questions & FSER Open Items Since 970516
NSD-NRC-97-5348, Forwards Assessment on Surge Line Flooding Effect on Low Power & Shutdown Risk in Response to 970905 Telcon Request
NRC-87-0084, Suppl 4 to Fermi 2 Nuclear Power Plant,Interim Startup Test Rept