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	Issue date	Title	Topic
ML23075A346	31 December 2022	WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 1 of 7)
ML23075A347	31 December 2022	WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 2 of 7)
ML23075A348	31 December 2022	WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 3 of 7)
ML23075A349	31 December 2022	WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 4 of 7)
ML23075A350	31 December 2022	WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 5 of 7)
ML23075A351	31 December 2022	WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 6 of 7)
L-PI-23-002, WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 7 of 7)	31 December 2022	WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 7 of 7)
ML21285A281	12 October 2021	Revised Pressure and Temperature Limits Report	Pressure and Temperature Limits Report
ML20272A293	28 September 2020	(PINGP) Unit 1 and 2 Revised Pressure and Temperature Limits Report	Pressure and Temperature Limits Report
L-PI-19-040, License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency	7 October 2019	License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency	Internal Flooding Probabilistic Risk Assessment Coatings Operating Basis Earthquake Aging Management Surveillance Frequency Control Program Large early release frequency Moisture barrier Maintenance Rule Program Fuel cladding Grace period
ML17279A124	30 September 2017	Enclosure 5 to L-PI-17-041, Westinghouse WCAP-17400-NP, Supplemental 1, Revision 2, Spent Fuel Pool Criticality Safety Analysis Supplemental Analysis Including the Storage of Ifba Bearing Fuel	Fuel cladding
L-PI-16-054, Pressure and Temperature Limits Report, Revision 5	22 June 2016	Pressure and Temperature Limits Report, Revision 5	Hydrostatic Pressure and Temperature Limits Report
L-PI-15-034, Pressure and Temperature Limits Report (PTLR) Revision 4	14 May 2015	Pressure and Temperature Limits Report (PTLR) Revision 4	Pressure and Temperature Limits Report
ML17297A323	14 November 2014	Enclosure 2 (Redacted): Seismic Walkdown Report, in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic Updated Transmittal for Prairie Island Unit 1	Safe Shutdown Unanalyzed Condition Safe Shutdown Earthquake Probabilistic Risk Assessment Fukushima Dai-Ichi Design basis earthquake Earthquake Scaffolding
ML16005A110	25 September 2014	Redacted 2014 Decommissioning Cost Analysis for the Prairie Island Nuclear Generating Plant
L-PI-14-045, Enclosure to L-PI-14-045, Transition Report, Revision 1	30 April 2014	Enclosure to L-PI-14-045, Transition Report, Revision 1
ML14030A540	27 February 2014	Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)	Safe Shutdown Boric Acid High winds Shutdown Margin Ultimate heat sink Time to boil Safe Shutdown Earthquake Internal Flooding Emergency Lighting FLEX Tornado Generated Missile Fukushima Dai-Ichi Design basis earthquake Frazil ice Battery sizing B.5.b Mitigating Strategies Earthquake
ML14041A204	26 February 2014	Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Prairie Island Nuclear Generating Plant, Units 1 and 2, TAC Nos.: MF0834 and MF0835	Safe Shutdown Boric Acid High winds Shutdown Margin Ultimate heat sink Tornado Missile Time to boil Safe Shutdown Earthquake Internal Flooding Emergency Lighting FLEX Fukushima Dai-Ichi Design basis earthquake Frazil ice Battery sizing B.5.b Mitigating Strategies Earthquake
ML13133A063	27 June 2012	H4, Rev. 27, Offsite Dose Calculation Manual (Odcm).	Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Process Control Program Annual Radiological Effluent Release Report
L-PI-10-076, Calculation No. GEN-PI-083, Revision 1, Locked Rotor Accident (LRA) Analysis Using AST, Attachment 5	23 July 2010	Calculation No. GEN-PI-083, Revision 1, Locked Rotor Accident (LRA) Analysis Using AST, Attachment 5	Deep Dose Equivalent
ML102100259	30 June 2010	Seismic Fragilities for Unit #1 and Unit #2 Turbine Building Piping and Equipment	Safe Shutdown Earthquake Probabilistic Risk Assessment Design basis earthquake Earthquake
ML083240545	6 November 2008	Final Report for the July 22, 2008, Radiological Emergency Preparedness (REP) Full Participation Plume Exposure Pathway Exercise	Deep Dose Equivalent
L-PI-08-090, Stress Analysis Summary Report of Preemptive Structural Weld Overlay for the Unit 2 Pressurizer Surge Nozzle	16 October 2008	Stress Analysis Summary Report of Preemptive Structural Weld Overlay for the Unit 2 Pressurizer Surge Nozzle	Weld Overlay Finite Element Analysis DM weld
ML082190013	7 August 2008	Monthly Operating Reports Second Quarter 2008	Reserve Station Service Transformer Power change
L-PI-05-054, Unit 2 Steam Generator Inspection Results - 15-Day Report	8 June 2005	Unit 2 Steam Generator Inspection Results - 15-Day Report
ML043570017	14 December 2004	from NMC Re Technical Evaluation of Proposed Method of Class 3 Pipe Leak Operability Determinations	Time of Discovery Aging Management Through-Wall Leak Scaffolding
ML050980256	28 October 2004	PPE-04-868, High Burnup Lead Test Assembly (LTA) Inspection Report, October 2004
L-PI-04-065, FAI/01-86, Rev 1 Gap - User Documentation	4 April 2004	FAI/01-86, Rev 1 Gap - User Documentation
L-PI-03-020, License Amendment Request Dated March 25, 2003 Safety Analyses Transition, Tabs F - H	25 March 2003	License Amendment Request Dated March 25, 2003 Safety Analyses Transition, Tabs F - H
L-PI-03-031, Cycle 21 Steam Generator Tube Support Plate Voltage Based Repair Criteria 90-Day Report	6 March 2003	Cycle 21 Steam Generator Tube Support Plate Voltage Based Repair Criteria 90-Day Report
ML030900342	6 March 2003	Request for Relief No.14 for Unit 1 3rd 10-Year Interval Inservice Inspection Program	Nondestructive Examination VT-2 Liquid penetrant
ML100840642	20 November 2002	Feasibly Study for Conversion of Prairie Island to Natural Gas Fired Generation. Submitted with Comments on Draft Generic Environmental Impact Statement for Prairie Island Nuclear Generating Plant, Units 1 and 2, Supplement 39 to NUREG- 143
ML023230354	7 November 2002	Pressure & Temperature Limits Report (PTLR) Revisions 2 & 3	Hydrostatic Pressure and Temperature Limits Report
ML021070419	15 April 2002	Response to a Request for Additional Information Regarding Request for Relief No. 11 for the Unit 1 3rd 10-Year Interval Inservice Inspection Program
NRC Generic Letter 1979-45	25 September 1979	NRC Generic Letter 1979-045: Transmittal of Reports Regarding Foreign Reactor Operation Experiences	Boric Acid

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