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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
- ML21274A022 + (ML21274A022)
- ML21274A023 + (ML21274A023)
- ML21274A024 + (ML21274A024)
- ML21274A025 + (ML21274A025)
- ML21274A026 + (ML21274A026)
- ML21274A027 + (ML21274A027)
- ML21274A029 + (ML21274A029)
- ML21274A030 + (ML21274A030)
- ML21274A031 + (ML21274A031)
- ML21274A032 + (ML21274A032)
- ML21274A039 + (ML21274A039)
- ML21274A040 + (ML21274A040)
- ML21274A041 + (ML21274A041)
- ML21274A042 + (ML21274A042)
- ML21274A043 + (ML21274A043)
- ML21274A044 + (ML21274A044)
- ML21274A046 + (ML21274A046)
- SECY-21-0092, Annual Update on the Status of Emergency Preparedness and Incident Response Programs Activities + (ML21274A049)
- ML21274A052 + (ML21274A052)
- L-2021-174, NextEra Energy Point Beach, LLC - Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) Set 9 Response + (ML21274A053)
- WBL-21-046, Unit 2 -Emergency Plan Implementing Procedure Revision + (ML21274A057)
- ML21274A058 + (ML21274A058)
- ML21274A068 + (ML21274A068)
- ML21274A069 + (ML21274A069)
- ML21274A070 + (ML21274A070)
- NL-21-0845, License Amendment Request: Revise Technical Specification 3.7.2 Limiting Condition for Operation to Remove One Main Steam Isolation Valve System + (ML21274A073)
- ML21274A075 + (ML21274A075)
- ML21274A076 + (ML21274A076)
- PMNS20211267, NRC Closed Meeting with the Pressurized Water Reactor Owners Group (PWROG) on the Review of Topical Report WCAP-17096 Revision 3, Reactor Internals Acceptance Criteria Methodology and Data Requirements + (ML21274A079)
- ML21274A081 + (ML21274A081)
- ML21274A083 + (ML21274A083)
- ML21274A084 + (ML21274A084)
- ML21274A085 + (ML21274A085)
- PMNS20201161, NRC Public Meeting with the Pressurized Water Reactor Owners Group (PWROG) to Discuss PWROGs Initial Developments on a Generic Concept of Risk-Informed Process for Exemptions (RIPE-G) + (ML21274A086)
- ML21274A121 + (ML21274A121)
- ML21274A150 + (ML21274A150)
- STC-24-058, Issuance of Proposed Rule and Notice of Availability of the Draft Generic Environmental Impact Statement for Advanced Nuclear Reactors (NUREG 2249) + (ML21274A151)
- ML21274A152 + (ML21274A152)
- ML21274A153 + (ML21274A153)
- ML21274A155 + (ML21274A155)
- PMNS20211271, NRC Public Meeting with the Pressurized Water Reactor Owners Group (PWROG) to Discuss PWROGs Initial Developments on a Generic Concept of Risk-Informed Process for Exemptions (RIPE-G) + (ML21274A156)
- PMNS20211139, NRC Staff Questions on GE-Hitachi Topical Reports for the BWRX-300 Small Modular Reactor Design + (ML21274A177)
- ML21274A182 + (ML21274A182)
- ML21274A276 + (ML21274A276)
- ML21274A369 + (ML21274A369)
- ML21274A417 + (ML21274A417)
- 05000321/LER-2021-001, Edwin L Hatch Nuclear Plant, Unit 1 Re Automatic Reactor Scram on Low Reactor Water Level Due to Loss of Reactor Feed Pumps + (ML21274A418)
- ML21274A517 + (ML21274A517)
- ML21274A551 + (ML21274A551)
- ML21274A555 + (ML21274A555)
- ML21274A556 + (ML21274A556)