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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 1994-49, Failure of Torque Switch Roll Pins +
- ML18041A029 +
- ML17059A362 +
- ML17059A422 +
- ML17059A424 +
- ML17059A361 +
- ML17310B460 +
- ML17310B459 +
- ML18037A983 +
- ML18037A982 +
- ML20070J504 +
- ML20070F439 +
- ML20070E496 +
- ML20070E364 +
- ML20070E086 +
- ML20070E048 +
- ML20070D954 +
- ML20070D947 +
- ML20070D769 +
- ML20070D694 +
- ML20070D528 +
- ML20073T096 +
- ML20073T085 +
- ML20073T072 +
- ML20072K764 +
- ML20071P116 +
- ML20071H411 +
- ML20071G954 +
- ML20071G928 +
- ML20071G909 +
- ML20071G377 +
- ML20071G370 +
- ML20071F822 +
- ML20071F814 +
- ML20071F809 +
- ML20205P195 +
- ML20205P164 +
- ML20217N593 +
- NRC-94-4191, Forwards APWR-0452-NP, AP600 Vortex Mitigator Development Test for RCS Mid-Loop Operation, & APWR-0452-P, AP600 Vortex Mitigator Development Test for RCS Mid-Loop Operation. APWR-0452-P Withheld (Ref 10CFR9.17)(a)(4)) +
- ST-HL-AE-4782, Clarifies Licensees Position for Demonstrating Operability of Pressurizer Power Operated Relief Valves,Per GL 90-06 +
- PY-CEI-NRR-1817, Forwards Rev 2 to PDB-F0001, COLR for Perry Nuclear Power Plant,Unit 1 Cycle 5 (Reload 4) & Rev 0 to GE Rept 23A7227, Suppl Reload Licensing Rept for Perry Nuclear Power Plant Unit 1 Reload 4 Cycle 5 +
- ML20265A584 +
- ML20265A579 +
- ML20071G130 +
- ML20071G167 +
- NRC-94-4178, Forwards AP600 Testing Program Repts (Proprietary) WCAP-14073,Rev 0,(Non-Proprietary) WCAP-14074,Rev 0, (Proprietary) WCAP-14112,Rev 0 & (Non-Proprietary) WCAP-14113,Rev 0.Proprietary Repts Withheld Per 10CFR2.790 +
- 05000331/LER-1994-009, :on 940609,hi Flow Alarm Was Received on Control Room Panel 1C03 Due to Failed Differential Pdt. Replaced Pdt W/Model That Is Not Conducive to Entrapment of Water in Its Housing & Procedure Revised +
- 05000373/LER-1994-008-04, :on 940607,determined That Relief Valve Setting Had Been Above 1400 Psig,Which Is Limit of Ts.Caused by Personnel Errors.Sblc Safety Relief Valves for Both Unit 1 & Unit 2 Were Reviewed +
- 05000458/LER-1994-015, :on 940606,fuse Blew While Test Equipment Manual Initiation Was Being Installed.Caused by Failure of Soldered Joint in Amphenol Connector.Blown Fuse Was Replaced & Faulty Connector Repaired +
- NRC-94-4193, Forwards Proprietary Quick Look 00238RP93, SPES-2 Cold Pre- Operational Test Results. Rept Provides NRC W/Info on AP600 Matrix Tests of Sufficient Depth to Enable Early Evaluation & Analysis of Test Results.Rept Withheld (Ref 10CFR2.790) +