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List of results

• ML050540132  + ((NMP-1). Technical Specifications, Defines the Term Instrument Channel Calibration, by Adding Two New Sentences Pertaining to Calibration of Resistance Temperature Detector or Thermocouple Sensors)
• ML050560274  + ((NMP1) - Evaluation of Upper Shelf Fracture Toughness Per 10 CFR Part 50, Appendix G)
• ML14181B086  + ((NMP1), ME8899, Email from Licensee to Confirm the Change from Nine Mile Point Nuclear Station LLC, to Exelon Generation LAR to Adopt NFPA 805)
• ML033070402  + ((NMPNS) Unit Nos. 1 and 2 - Audit of the Licensees Management of Regulatory Commitments)
• ML18228A725  + ((NOED No. 18-1-01))
• ML071290155  + ((NPA-PD) Letter to Mary Lampert from the Commonwealth of Massachusetts Executive Office of Heath and Human Services, Department of Public Health, Regarding Child Heath Statistics)
• ML071720161  + ((NPA-PD-LR) Email: PIC - Proposal for Information Collection to Address Compliance with the Clean Water Act 316(b) Phase II Regulations)
• L-10-161, (NPDES Permit No. 3IB00016*ID), Request for Approval of an Essential Maintenance Discharge Change  + ((NPDES Permit No. 3IB00016*ID), Request for Approval of an Essential Maintenance Discharge Change)
• L-12-182, (NPDES Permit No. 3IB00016*JD), Request for Approval of an Essential Maintenance Discharge Change  + ((NPDES Permit No. 3IB00016*JD), Request for Approval of an Essential Maintenance Discharge Change)
• ML073240582  + ((NPDES Permit No. Ga 0026786) Quarterly Operational Monitoring Report)
• ML052550490  + ((NRC Bulletin 2003-01), Response to Third NRC Request for Additional Information)
• IR 05000483/2010001  + ((NRC Inspection Report 05000483-10-001))
• ML21119A287  + ((Naps), Unit 1 and 2 - Subsequent License Renewal Application (SLRA) Response to NRC Request for Additional Information Safety Review - Set 2 and Flow Accelerated Corrosion Program Enhancement Completion)
• ML110060011  + ((Naps), Unit No. 1, Third 10-Year Inservice Inspection Interval (ISI) Program, Relief Request (RR) N1-13-PRT-004, Part a Through Part G)
• ML21280A357  + ((Naps), Units 1 and 2 - Comments on Draft Plant-Specific Supplement 7, Second Renewal to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Subsequent License Renewal for Facility.)
• ML21210A396  + ((Naps), Units 1 and 2 - Subsequent License Renewal Application (SLRA) Response to NRC Request for Additional Information Safety Review - Set 4 and Supplement 3)
• ML21258A354  + ((Naps), Units 1 and 2 - Subsequent License Renewal Application (SLRA) Response to NRC Request for Confirmation of Information Set 2 Safety Review)
• ML21341B437  + ((Naps), Units 1 and 2 - Subsequent License Renewal Application Responses to NRC Request for Additional Information Safety Review - Set 5)
• ML21076B027  + ((Naps), Units 1 and 2 - Subsequent License Renewal Application (SLRA) Additional Document in Response to Environmental Audit Architectural Survey)
• ML22223A145  + ((Naps), Units 1 and 2 - Subsequent License Renewal Application (SLRA) Second 10 CFR 54.21(b) Annual Amendment)
• ML21217A187  + ((Naps), Units 1 and 2 - Subsequent License Renewal Application First 10 CFR 54.21 (B) Annual Amendment)
• ML21053A433  + ((Naps), Units 1 and 2 - Subssequent License Renewal Application (SLRA) Environmental Review - Response to NRC Request for Additional Information)
• ML21035A303  + ((Naps), Units 1 and 2 - Update to Subsequent License Renewal Application (SLRA) Supplement 1)
• ML21147A293  + ((Naps), Units 1 and 2 Subsequent License Renewal Application (SLRA) Response to NRC Request for Additional Information Safety Review - Set 3 and Administrative Change to SLRA Table A4.0-1, Item 25)
• ML103060097  + ((Naps), Units 1 and 2, Fourth 10-Year Inservice Testing Interval Program, Pumps and Valves Relief Request (RR))

• ML103630082  + ((Narucs) Certification of Licensing Support Network Supplementation)

• ML17121A270  + ((Nei), Comments on Draft Implementation Plan to Ensure NRC Staff Readiness for AP1000 Operations, Revision 0)
• ML19316C714  + ((Nei), NRC Review and Endorsement of NEI 17-04, Model SLR New and Significant Assessment Approach for SAMA, Revision 1)
• ML19316C713  + ((Nei), NRC Review and Endorsement of NEI 17-04, Model SLR New and Significant Assessment Approach for SAMA, Revision 1)
• ML17031A171  + ((Nei), Request for Endorsement of Seismic Evaluation Guidance: Spent Fuel Pool Integrity Evaluation (EPRI 3002009564))
• ML23214A253  + ((Nei), Request for Review and Endorsement of NEI 99-04, Rev. 1, Guideline for Managing NRC Commitment Changes)
• ML22356A124  + ((Nei), Resolution of Revised NRC Staff Comment 6 NEI 99-01, Revision 7, Draft G)
• ML22356A125  + ((Nei), Responses to NRC Staff Comments on NEI 99-01, Revision 7, Draft G)
• Regulatory Guide 1.226  + ((New Regulatory Guide, Draft Was Issued as DG-1301, Dated November 2015) Flexible Mitigation Strategies for Beyond-Design-Basis Events)
• ML103500364  + ((Nmpns), Response to Request for Additional Information Regarding NMPNS, Unit No. 2 - the License Amendment Request for Extended Power Uprate Operation (TAC No. ME1476) - Spent Fuel Pool Criticality Analysis)
• ML030060139  + ((Non Safeguards Portion) California Energy Commission, Request for State of California to Observe Inspection at Diablo Canyon Plant)
• ML120340190  + ((Non- Proprietary) Licensee Slides from 1/30/12 Meeting with Entergy Operations, Inc)
• ML25100A045  + ((Non-Proprietary) Braidwood Station, Units 1 and 2, and Byron Station, Unit Nos. 1 and 2 - Request for Additional Information in Support of Review of License Amendment Request to Transition to Framatome Gaia Fuel)
• ML120720331  + ((Non-Proprietary) Request for Additional Information, Nrr/De/Emcb Review of Steam Dryer, Round 6, Amendment Request for Extended Power Uprate to Increase Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt)
• ML090570036  + ((OCNGS) - Audit of the Exelons Management of Regulatory Commitments)
• ML051940581  + ((OCNGS) - Final Accident Sequence Precursor Analysis of May 20, 2003, Operational Event)
• ML032650616  + ((OCNGS) - Relief Request Review, Alternative and Reliefs Concerning the Fourth 10-Year Interval Inservice Inspection Program)
• ML19157A023  + ((OEDO-15-00479) 2.206 Petition Regarding Pilgrim Nuclear Power Stations Current Licensing Basis for Flooding Status Update (CAC No. MF6460; EPID L-2015-CRS-0002))
• ML18158A225  + ((OEDO-15-00479) Pilgrim Nuclear Power Station - 2.206 Petition Regarding Pilgrim Nuclear Power Station - Current Licensing Basis for Flooding - 60-Day Status Report (CAC No. MF6460; EPID L-2015-CRS-0002))
• ML18026A973  + ((OEDO-16-00722-OCIO) Memorandum Response to Status of Recommendations: Cyber Security Act of 2015 for the Nuclear Regulatory Commission (OIG-16-A-18))
• OIG-17-A-03, (OEDO-17-00459) Response to the Office of the Inspector Generals Independent Evaluation of NRCs Implementation of the Federal Information Security Modernization Act of 2014 for Fy 2016, Dated December 28 2016 (OIG-17-A-03)  + ((OEDO-17-00459) Response to the Office of the Inspector Generals Independent Evaluation of NRCs Implementation of the Federal Information Security Modernization Act of 2014 for Fy 2016, Dated December 28 2016 (OIG-17-A-03))
• OIG-17-A-16, (OEDO-17-00522) Response to Status of Recommendations: the Office of the Inspector Generals Audit Report of the Nuclear Regulatory Commissions Adoption of Cloud Computing (OIG-17-A-16)  + ((OEDO-17-00522) Response to Status of Recommendations: the Office of the Inspector Generals Audit Report of the Nuclear Regulatory Commissions Adoption of Cloud Computing (OIG-17-A-16))
• ML18009A241  + ((OEDO-17-00799-OCIO) Memorandum Response to the Office of the Inspector Generals Evaluation of the Nuclear Regulatory Commissions Shared Drive (OIG-18-A-06))
• ML19151A331  + ((OEDO-19-00053)10 CFR 2.206 Petition Involving Grand Gulf Nuclear Station)
• OI 1-2003-031, (OI 1-2003-031 & 1-2003-032) to Determine Whether (1) a Manager at the IPEC Deliberately Violated a Site Procedure When an Employee Took an NRC Exam for Possible SRO Certification Without a Classroom Proctor Present and (2) Whether a F  + ((OI 1-2003-031 & 1-2003-032) to Determine Whether (1) a Manager at the IPEC Deliberately Violated a Site Procedure When an Employee Took an NRC Exam for Possible SRO Certification Without a Classroom Proctor Present and (2) Whether a Former)
• ML041330088  + ((OI Case 1-2003-018) on 2/21/03, to Determine Whether an Exelon Nuclear Employee at the Limerick Generating Station Was Discriminated Against for Having Raised Concerns Re Limerick Emergency Preparedness and the Exelon Standard Emergency Pl)