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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
- Information Notice 1991-05, Intergranular Stress Corrosion Cracking in Pressurized Water Reactor Safety Injection Accumulator Nozzles +
- ML17157A809 +
- ML17157A571 +
- ML17328A880 +
- ML17328A879 +
- ML17328A878 +
- 05000311/LER-1991-001, :on 910104,discovered That Hourly Roving Fire Watch Patrol for Several Areas Not Completed.Caused by Personnel Error.Responsible Individual Terminated & Event Discussed W/Appropriate Personnel +
- ML18057A810 +
- ML20029A212 +
- ML20029A162 +
- ML20070D590 +
- ML20069N606 +
- ML20067E427 +
- ML20067D654 +
- ML20067C557 +
- ML20067B324 +
- ML20067B260 +
- ML20067B247 +
- ML20066L414 +
- ML20066K906 +
- ML20066K450 +
- ML20066K271 +
- ML20066K257 +
- ML20066K252 +
- ML20066K005 +
- ML20066J806 +
- IA-91-162, Forwards Details of Allegation RI-90-A-225 for Review & Followup within 30 Days of Ltr Receipt +
- ML20126B378 +
- ML20266A816 +
- ML20261E163 +
- RBG-34408, Responds to Re Implementation of Alternate Rod Injection Sys Diversity Requirements,Per 10CFR50.62 (ATWS Rule) for BWRs +
- RBG-34407, Forwards Rev 0 to Topical Rept EA-CA-91-0001-M, Steady State Core Physics Methods for BWR Design & Analysis for Review & Approval.Rept Submitted,Per 900712 & 1218 Meetings W/Nrc +
- B13723, Requests Extension to Previously Filed & Approved Request for Relief from ASME Section Xi,To Allow Continued Use of Temporary Rubber Expansion Joint in Pipe Until Replacement Is Available +
- RBG-34397, Forwards Fitness for Duty Program Performance Data Semiannual Rept for Jul-Dec 1990,per 10CFR26.71(d) +
- ST-HL-AE-3676, Responds to NRC Re Violations Noted in Insp Repts 50-498/90-34 & 50-499/90-34.Corrective actions:13.8-kV Breaker Test Procedures & Associated Surveillance Procedures Revised & Technical Review Performed on Fcr 90-1891 +
- A07623, Responds to NRC Re Generic Ltr 88-17, Loss of Dhr. Equipment Mods for Programmed Enhancements Accomplished During 1990 Refueling Outage.Summary of Instrumentation Used to Monitor Status of RCS Encl +
- LD-91-006, Forwards Summary of Amend I to Std SAR for Design Certification,For Info & Planning Purposes +
- PY-CEI-NRR-1288, Forwards Proprietary NEDE-31567-P,addendum, Addendum to Perry 1 Reactor Internals Vibration Measurements (In-Core Guide Tube Fatigue Usage During Single Loop Operation). Encl Withheld (Ref 10CFR2.790) +
- 05000265/LER-1991-001-01, :on 910102,severe Packing Leak on HPCI Turbine Steam Supply Isolation Motor Operated Valve Discovered. Caused by Steam Cut on Valve Stem.Valve Repacked & Stem to Be Repaired &/Or Replaced +
- IR 05000327/1991001 +
- IR 05000443/1990085 +
- ML20029A103 +
- ML20029A117 +
- ML19336D066 +
- ML19336D168 +
- ML19336D057 +
- ML19336D042 +
- ML19336D161 +
- ML20029A365 +
- ML20029B325 +