SNRC-1283, BWR Owners Group Rept on Operational Design Basis of Selected Safety-Related Motor-Operated Valves
AECM-86-0121, Responds to NRC Re Violations Noted in Insp Rept 50-416/86-04.Corrective Actions:Nonseismic Relays Replaced W/Properly Qualified Agastat ETR Relays Per Design Change Package 84/3516.Relays Successfully Bench Tested
NG-94-3575, Request for TS Change (RTS-267),replacing Instrument Setpoint W/Ref to Appropriate Citation in Offsite Dose Assessment Manual & Modifying Operability Requirement & Required Action for Inoperable Offgas Vent Stack RMs
05000331/LER-1998-002, :on 980403,unexpected ESF Actuation Was Noted. Caused by Inadequate Procedure.Relay Was Replaced & STP Revised
NUREG-1708, Forwards NUREG-1708, External Regulation of DOE Nuclear Facilities.A Pilot Program. Results in Rept Differ Considerably from Results Presented in Lawrence Berkeley Natl Lab Pilot Project Repts
05000302/LER-1983-011-03, /03L-0:on 830305,during Normal Operation,Two Holes Discovered in safety-related Fire Wall.Addl Investigation Revealed Two More Holes.Caused by Inadequate Mod Process.Mod Process Will Be Revised
05000446/LER-1994-012, :on 940815,manual Reactor Trip & Auxiliary Feedwater auto-start Occurred Due to Steam Generator lo-lo Level Signal.Bushing Replaced & Transformer Returned to Svc
05000333/LER-1982-045-03, /03L-0:on 821006,isolation Valves 02-39 & 40 Associated W/Penetration X-41 Failed to Isolate on All Signals.Caused by Failure to Update FSAR & Tech Specs to Reflect Change in Signals During Const.Valves Closed
B14623, Informs of Completion of Mod of Commitment Re Immediate Corrective Action for Violation EA 89-124.Survey Requirements for Vehicles Leaving Protected Area Will Be Revised to Allow Certain Vehicles to Be Exempt from Survey
05000317/LER-1990-017, :on 900505,pin Hole Leak Observed in Discharge Piping of Saltwater Pump 13.Caused by Localized Corrosion. Leaking Spool Piece Removed & Blank Flange Installed
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 .
L-05-007, Discharge Monitoring Report (NPDES) Permit No. PA0025615
B13666, Rev 4 to Millstone Nuclear Power Station Unit 1 Inservice Test Pump & Valve Program