L-2002-233, Westinghouse Report WCAP-15945-NP, Rev. 1, Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation: St. Lucie Unit 1
JPN-95-024, Forwards Rev 3 to Reload 11/Cycle 12 Colr
SNRC-1168, Formalizes Util Understanding of NRC Position on Applicant Resolution of Fire Protection Issues Outlined in Insp Rept 50-322/84-46 & Associated Notice of Deviations.Calculation Summaries Encl
SNRC-1018, Interim Deficiency Rept Re Failure of Turbocharger on Emergency Standby Diesel Generator.Temporary Bypass Valve Around Turbocharger Prelube Drip Line Orifice Installed. W/Certificate of Svc.Related Correspondence
TXX-6713, Final Supplemental Deficiency Rept CP-85-40 Re Adequacy of Flux Mapping Seal (Fms) Table Restraints Under Seismic Loads.Initially Reported on 851126.Unit 1 Fms Mods Complete. Unit 2 Mods Scheduled for Completion by 880515
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
AECM-81-477, Forwards marked-up Draft of Radiological Ets.Three Open Items Discussed Re Radwaste Discharge Monitor Operation, Channel Function Test for Ventilation Sys Flow Rate Monitor & Accuracy of FSAR Figure 9.4-11
A01852, Forwards Addl Info Re SEP Topic II-3.A, Hydrologic Description & SEP Topic II-3.B, Flooding Potential & Protection Requirements, Per NRC 810710 Request.Eight Oversize Drawings Encl.Aperture Card Is in PDR
05000302/LER-1979-011-03, /03L-0 on 790210:reactor Coolant Dose Equivalent I-131 Exceeded Tech Spec Limits.Caused by Expected Spike Following Reactor Trip & Known Leaking Fuel Pins.Reactor Coolant Sys Cleanup Returned to Acceptable Limits
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 .
RA18-059, Inservice Testing Program Plan, Technical Position TP-05
RBG-47913, Request for Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii) Proposed Alternative to CFR 50.55a Examination Requirements for Third Interval Volumetric Exams (RBS-ISI-021)
ET 07-0020, Response to NRC Requests for Additional Information Related to Wolf Creek Generating Station License Renewal Application
HL-5579, Forwards Proprietary & non-proprietary Response to 980210 RAI Re License Amend Request to Increase Authorized Max Power Level to 2,763 Mwt.Topical Rept NEDO-32749 Encl. Proprietary Info Withheld