Sujata Goetz# QUERY93bf184ea67c66d3327d5fddecb4f8c7
Sujata Goetz# QUERYa6e222de17bd13570b3f85f2655dd9dc
Sujata Goetz# QUERYa8876768e9fd1663fa517648b273b1f8
Sujata Goetz OR Sujata Goetz
Sujata Goetz# QUERY187fb1e8eed7317df199915424e80a28
Sujata Goetz# QUERY1c529054506a27cd573c17eeead95816
Sujata Goetz# QUERYc53e5a299da8baeb9afa8a4c91ccfe56
Sujata Goetz
Sujata Goetz# QUERY84c2c32b85d4b3a4a692aa9173147126
Sujata Goetz# QUERYaf96e49475c6ffcb4cfc698801e06b3d
NRC/NRR/DORL/LPL3 false
Sujata Goetz# QUERY9068daab15ba8a4d3e3f164cab95ceaf
NRC/NRR/DORL/LPL3 true
Sujata Goetz# QUERY889eb775d96e97d45366bf5e3243c082
NRC Headquarters
Sujata Goetz# QUERYde076fd0735aa8b856faf204727da28d
NRC-17-0036, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications for Emergency Core Cooling System Instrumentation and Reactor Core Isolation Cooling System Instrumentation
NRC-17-0066, Supplemental Information Regarding License Amendment Request to Eliminate Main Steam Line Radiation Monitor Reactor Trip and Primary Containment Isolation System Group 1 Isolation Functions
NRC-16-0049, Response to Request for Additional Information Regarding License Amendment Request to Revise Integrated Leak Rate Test - Type a and Type C Test Intervals
NRC-16-0038, Response to Request for Additional Information Regarding Revised Relief Request PRR-007 for the Inservice Testing Program Third 10-Year Interval
RIS 2013-08, Withdrawn RIS 2013-08, Process for Scheduling Acceptance Reviews of New Reactor Licensing and Design Certification Applications and Process for Determining Budget Needs for Fiscal Year 2016
NRC-18-0014, Response to Request for Additional Information Regarding Relief Request No. RR-A37, Revision 1, for the Inservice Inspection Program Third 10-Year Interval
NRC-18-0001, DTE Energy Company - Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification Section 3.7.2
NRC-18-0032, Response to NRC Request for Additional Information for License Amendment Request to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
NRC-18-0040, Supplemental Information in Response to NRC Request for Additional Information for License Amendment Request to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
PMNS20180847, Telephone Conference with DTE Regarding Its License Amendment Request to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
NRC-18-0045, Response to NRC Requests for Additional Information for License Amendment Request to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
PMNS20180707, Pre-Submittal Meeting with DTE Energy to Discuss Fermi 2s Plans to Submit a New License Amendment Request
PMNS20181217, Pre-Submittal Meeting with DTE Energy to Discuss Plans to Submit a New License Amendment Request Regarding a 24 Month Fuel Cycle for Fermi 2
PMNS20200117, Pre-Submittal Meeting with Talen Energy Susquehanna Steam Electric Station, Units 1 and 2, Proposed License Amendment Request to Create New Condition for Inoperable Manual Synchronization Circuit and Institute Completion Time of 14 Days
NRC-19-0029, Withdrawal of the Inservice Inspection / Nondestructive Examination Program Relief Request RR-A36 for the Fourth Ten-year Interval
NRC-19-0039, Response to NRC Request for Additional Information for License Amendment Request to Revise Technical Specification 3.3.5.3, Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation
NRC-19-0045, Response to Request for Additional Information Regarding Snubber Program Relief Request RR-S1 for the Fourth 10-Year Interval
NRC-19-0042, Responses to Requests for Additional Information Regarding Relief Requests for the Inservice Inspection Program Fourth Ten-year Interval
NRC-19-0061, Withdrawal of the Inservice Testing Program Relief Requests VRR-004 and VRR-007 for the Fourth Ten-Year Interval
NRC-19-0067, Submittal of Revised Valve Relief Request VRR-004 for the Inservice Testing Program Fourth 10-Year Interval
NRC-19-0085, DTE Energy Company Transmittal of Revision 1 of the Core Operating Limits Report for Cycle 20
NRC-20-0011, Transmittal of the Core Operating Limits Report for Cycle 21
PMNS20201308, Meeting with NextEra Energy/Florida Power & Light Company to Discuss Generic Safety Issue-191/Generic Letter 2004-02 Closeout Letters
PMNS20210002, Pre-Application Meeting for TSTF-505 Application for Susquehanna Steam Electric Station
NRC-20-0046, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Utilize Neutron Absorbing Inserts in Criticality Safety Analysis for Fermi 2 Spent Fuel Storage Racks
PMNS20220029, License Amendment Regarding Operating Limits Report (COLR)
PMNS20230063, Notice of Meeting with Constellation Energy Generation, LLC, (Constellation) to Discuss Its Requests for Alternatives for Certain Steam Generator Weld Inspections
PMNS20230288, Public Pre-Application Meeting for Peach Bottom Atomic Power Station Planned Exemption Request from Part 26 Work-Hour Rules
NRC-24-0032, Transmittal of the Core Operating Limits Report for Cycle 23
NL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions
NRC-23-0079, Transmittal of Revision 1 of the Core Operating Limits Report for Cycle 22
NRC-22-0006, Transmittal of the Core Operating Limits Report for Cycle 22
PMNS20190100, Pre-Submittal Meeting with DTE Energy to Discuss Fermi 2s Plans to Submit a New License Amendment Request
NRC-18-0019, Response to NRC Request for Additional Information for License Amendment Request to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
NRC-18-0016, Response to Request for Additional Information (Set 2) Regarding License Amendment Request to Revise Technical Specifications to Eliminate Main Steam Line Radiation Monitor Reactor Trip and Primary Containment Isolation System Group 1
NRC-18-0015, Response to Request for Additional Information (Set 1) Regarding License Amendment Request to Revise Technical Specifications to Eliminate Main Steam Line Radiation Monitor Reactor Trip and Primary Containment Isolation System Group 1
PMNS20220027, License Amendment Regarding Operating Limits Report (COLR)
NRC-25-0030, Transmittal of the Core Operating Limits Report for Cycle 23, Revision 1