| ML15182A067 | 20 July 2015 | Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(F), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near Term Task Force Review of Insights From.. | Safe Shutdown Earthquake
Fukushima Dai-Ichi
Earthquake |
| ML15219A566 | 29 July 2015 | MNS-TS-5,6 - Distribution to Manual Holders - Amendment 278/258 | Shutdown Margin
Post Accident Monitoring
Nondestructive Examination
Annual Radiological Environmental Operating Report |
| ML15246A145 | 11 August 2015 | Submittal of 10 CFR 71.95 Report on the 8-120B Cask | |
| ML15313A164 | 8 October 2015 | Submittal of 10 CFR 71.95 Report on the 8-120B Cask | |
| ML16237A354 | 31 August 2016 | Staff Review of Spent Fuel Pool Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1 | Safe Shutdown Earthquake
Fukushima Dai-Ichi |
| ML16293A666 | 31 October 2016 | Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism Reevaluation (CAC Nos. MF3623 and MF3624) | High winds
Hydrostatic
FLEX
Fukushima Dai-Ichi
Earthquake |
| ML16294A253 | 12 October 2016 | Issue MNS Technical Specification 5.6 Rev. 2 Amend. 288/267 | Shutdown Margin
Post Accident Monitoring
Nondestructive Examination
Annual Radiological Environmental Operating Report |
| ML16363A354 | 9 December 2016 | 54003-CALC-01, Evaluation of Risk Significance of Permanent ILRT Extension. | Hot Short
Safe Shutdown
High winds
Mission time
Fire Barrier
Tornado Missile
Internal Flooding
Hydrostatic
Probabilistic Risk Assessment
Fire impairment
Thermoset
Large early release frequency
TORMIS
Earthquake
Fire Protection Program
Fire Watch |
| ML17171A277 | 12 June 2017 | Selected Licensee Commitments List of Revised Effected Sections | |
| ML18135A072 | 30 April 2018 | ANP-3658, Revision 0, Evaluation of the McGuire Units 1 and 2 Upflow Modification for 60 Years. | Aging Management |
| ML19058A416 | 8 March 2019 | Staff Evaluation Related to Reactor Vessel Internals Inspection Plan Based on MRP-227-A | Aging Management
Stress corrosion cracking
License Renewal
Power change |
| MNS-14-029, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of The. | 20 March 2014 | Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of The. | Safe Shutdown Earthquake
Probabilistic Risk Assessment
Fukushima Dai-Ichi
Earthquake
Seismic Walkdown Report |
| MNS-14-030, Annual Commitment Change Report | 19 March 2014 | Annual Commitment Change Report | |
| MNS-14-097, Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review. | 17 December 2014 | Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review. | Safe Shutdown Earthquake
Probabilistic Risk Assessment
FLEX
B.5.b
Fukushima Dai-Ichi
Earthquake
Power-Operated Valves |
| MNS-15-004, Annual Commitment Change Report | 29 January 2015 | Annual Commitment Change Report | |
| MNS-15-014, LTR-PAFM-14-114-NP, Rev. 0, Technical Justification to Support Extended Volumetric Examination Interval for McGuire, Unit 1, Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds (Non-Proprietary) | 28 February 2015 | LTR-PAFM-14-114-NP, Rev. 0, Technical Justification to Support Extended Volumetric Examination Interval for McGuire, Unit 1, Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds (Non-Proprietary) | Safe Shutdown Earthquake
Hydrostatic
Stress corrosion cracking
Eddy Current Testing
Earthquake
Dissimilar Metal Weld
DM weld
Affidavit |
| MNS-15-072, Selected Licensee Commitment Special Report 2015-01, Nuclear Condition Report No. 1943414, Standby Shutdown System Was Non-functional for a Period Greater than 7 Days | 10 September 2015 | Selected Licensee Commitment Special Report 2015-01, Nuclear Condition Report No. 1943414, Standby Shutdown System Was Non-functional for a Period Greater than 7 Days | Safe Shutdown
Ultimate heat sink
Functionality Assessment
Earthquake
Fire Protection Program |
| MNS-16-008, Expedited Seismic Evaluation Process (ESEP) Closeout, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.. | 4 February 2016 | Expedited Seismic Evaluation Process (ESEP) Closeout, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.. | Safe Shutdown Earthquake
Probabilistic Risk Assessment
FLEX
B.5.b
Fukushima Dai-Ichi
Earthquake
Power-Operated Valves |
| MNS-17-050, Review Request for the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A | 13 December 2017 | Review Request for the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A | Aging Management
Stress corrosion cracking
License Renewal
Power change
Power Uprate
Affidavit |
| NEI 99-04, McGuire Nuclear Station, Units 1 and 2 - Annual Commitment Change Report | 29 March 2012 | McGuire Nuclear Station, Units 1 and 2 - Annual Commitment Change Report | |
| NEI 99-04, McGuire, Units 1 & 2 - Annual Commitment Change Report | 31 March 2010 | McGuire, Units 1 & 2 - Annual Commitment Change Report | |
| RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 | 30 May 2019 | Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 | |
| RA-19-0245, of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology | 25 October 2021 | of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology | Fuel cladding
Affidavit |
| RA-20-0363, Post Accident Monitoring Report 369-2020-01 | 1 December 2020 | Post Accident Monitoring Report 369-2020-01 | Reactor Vessel Water Level
Post Accident Monitoring |