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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 2016-08, Inadequate Work Practices Resulting in Faulted Circuit Breaker Connection  + (ML16104A214)
• ML16104A220  + (ML16104A220)
• PLA-7452, Guarantee of Payment of Deferred Premiums, Per 10 CFR 140.21  + (ML16104A226)
• ML16104A245  + (ML16104A245)
• ML16104A287  + (ML16104A287)
• ML16104A295  + (ML16104A295)
• NUREG-2193 Volume 2, Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station. Docket Number 50-346, Firstenergy Nuclear Operating Company Sections 4 to 6 Appendices  + (ML16104A301)
• ML16104A316  + (ML16104A316)
• ML16104A320  + (ML16104A320)
• NUREG-2193, Suppl 1, Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station. Docket Number 50-346, Firstenergy Nuclear Operating Company  + (ML16104A350)
• ML16104A351  + (ML16104A351)
• ML16104A352  + (ML16104A352)
• Press Release-II-16-021, NRC Schedules Open House to Discuss Agencys 2015 Assessment of Browns Ferry Nuclear Plant  + (ML16104A353)
• ML16104A382  + (ML16104A382)
• ML16104A387  + (ML16104A387)
• 05000325/LER-2016-001, Regarding Electrical Bus Fault Results in Lockout of Startup Auxiliary Transformer and Loss of Offsite Power  + (ML16104A391)
• 05000327/LER-2016-001, Regarding Automatic Safety Injection Due to Low Steam Line Pressure on Loop 2 Main Steam  + (ML16104A392)
• ML16104A402  + (ML16104A402)
• ML16104A426  + (ML16104A426)
• ML16104A446  + (ML16104A446)
• ML16104A459  + (ML16104A459)
• ML16105A008  + (ML16105A008)
• IA-16-010, Acknowledgement of Response to Notice of Violation (NRC Investigation Report No. 1-2015-030)  + (ML16105A027)
• ML16105A049  + (ML16105A049)
• FOIA/PA-2016-0340  + (ML16105A115)

• FOIA/PA-2016-0420  + (ML16105A116)

• ML16105A121  + (ML16105A121)
• FOIA/PA-2016-0365  + (ML16105A172)
• ML16105A178  + (ML16105A178)
• ML16105A179  + (ML16105A179)
• RS-16-080, Clinton, Unit 1 - 90-Day Notification Prior to First Storage of Spent Fuel  + (ML16105A179)
• ML16105A211  + (ML16105A211)
• ML16105A213  + (ML16105A213)
• 05000321/LER-2016-003, Regarding Reactor Coolant System Piping Has Unacceptable Weld Indication Discovered During Refueling Outage  + (ML16105A219)
• ML16105A232  + (ML16105A232)
• 05000311/LER-2016-003, Regarding Automatic Reactor Trip Due to Main Generator Protection Trip  + (ML16105A264)
• U-604269, Operational Safety Review Team (Osart) Follow Up Mission Report  + (ML16105A276)
• ML16105A282  + (ML16105A282)
• ML16105A297  + (ML16105A297)
• Press Release-II-16-023, NRC Schedules Open House to Discuss 2015 Summer Nuclear Plant Performance and Construction Inspections of New Units  + (ML16105A318)
• Press Release-II-16-022, NRC Schedules Open House and Meeting to Discuss Assessment of Sequoyah Nuclear Plant and NRC Research Analyzing Unlikely Accidents  + (ML16105A319)
• ML16105A320  + (ML16105A320)
• ML16105A326  + (ML16105A326)
• ML16105A334  + (ML16105A334)
• JAFP-16-0060, Extension to Commitments Made in Response to March 12, 2012, Information Request Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3, Emergency Communication and Staffing Assessments  + (ML16105A358)
• JAFP-16-0061, Request for Relaxation of March 12, 2012 Commission Orders Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and Reliable Spent Fuel Pool Instrumentation  + (ML16105A379)
• NG-16-0080, Response to Request for Additional Information, License Amendment Request (TSCR-153) to Reduce the Reactor Steam Dome Pressure Specified in the Reactor Core Safety Limits  + (ML16105A388)
• 0CAN041603, Annual Occupational Radiation Exposure Report  + (ML16105A391)
• ML16105A409  + (ML16105A409)
• ML16105A412  + (ML16105A412)
• RS-16-077, Response to Request for Additional Information Regarding Request for License Amendment to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls  + (ML16105A421)