Semantic search

This page or action requires JavaScript to work. Please enable JavaScript in your browser or use a browser where it is supported, so that functionality can be provided as requested. For further assistance, please have a look at the noscript help page.

Search Clear all entries

	Issue date	Title	Topic
NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations	14 July 2023	Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations	Weld Overlay Moisture barrier Through-Wall Leak
NMP1L3517, Proposed Alternative Associated with a Weld Overlay Repair to the Torus	29 March 2023	Proposed Alternative Associated with a Weld Overlay Repair to the Torus	Weld Overlay
NMP2L2811, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2022 Owner'S Activity Report for RFO-18 Inservice Examinations	13 May 2022	Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2022 Owner'S Activity Report for RFO-18 Inservice Examinations
ML21189A026	28 June 2021	Fifth Inservice Inspection Interval, First Inservice Inspection Period 2021 Owner'S Activity Report for RFO-26 Inservice Examinations
NMP1L3356, Relief Requests Associated with Pump Periodic Verification Tests for the Fifth Ten-Year Inservice Test Interval	8 October 2020	Relief Requests Associated with Pump Periodic Verification Tests for the Fifth Ten-Year Inservice Test Interval	Fuel cladding
NMP2L2755, Fourth Inservice Inspection Interval, First Inservice Inspection Period, 2020 Owner'S Activity Report for RFO17 Inservice Examinations	8 January 2020	Fourth Inservice Inspection Interval, First Inservice Inspection Period, 2020 Owner'S Activity Report for RFO17 Inservice Examinations	Coatings VT-2 Through-Wall Leak
NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879	16 October 2019	Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879	Boric Acid Nondestructive Examination
ML19267A024	24 September 2019	End of Interval Relief Associated with the Third Ten-Year Inservice Inspection (ISI) Interval
NMP1L3309, Submittal of the Snubber IST Program Plan for the Unit 1 Fifth 10-Year Interval and the Unit 2 Fourth 10-Year Interval	6 September 2019	Submittal of the Snubber IST Program Plan for the Unit 1 Fifth 10-Year Interval and the Unit 2 Fourth 10-Year Interval
NMP2L2700, Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants	30 April 2019	Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants	Boric Acid Loop seal Nondestructive Examination
ML18207A406	17 July 2018	Third Inservice Inspection Interval, Third Iservice Inspection Period 2018 Owner'S Activity Report for RF0-16 Lnservice Examinations
ML18018A962	18 January 2018	Preservice Inspection Plan - Preservice Testing - Component Supports
ML18018A961	18 January 2018	Preservice Inspection Plan	Stroke time Hydrostatic Squib VT-2 Cold shutdown justification Liquid penetrant
ML17164A181	6 June 2017	Fourth Inservice Inspection Interval, Third Inservice Inspection Period 2017 Owner'S Activity Report for RF0-24 Inservice Examinations	EVT-1
NMP2L2620, Submittal of Post Extended Power Uprate Steam Dryer Inspection Results and Long-term Steam Dryer Inspection Plan in Accordance with Operating License Conditions 2.C.(20)(f), 2.C.(20)(g) and 2.C.(20)(h)	1 August 2016	Submittal of Post Extended Power Uprate Steam Dryer Inspection Results and Long-term Steam Dryer Inspection Plan in Accordance with Operating License Conditions 2.C.(20)(f), 2.C.(20)(g) and 2.C.(20)(h)	EVT-1
ML16216A149	25 July 2016	Third Inservice Inspection Interval, Second Inservice Inspection Period 2016 Owner'S Activity Report for RFO-15 Inservice Examinations
ML15191A385	9 July 2015	Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2015 Owner'S Activity Report for RFO-23 Inservice Examinations	EVT-1
ML15155A591	3 June 2015	End of Interval Relief Request Associated with the Second 10- Year Risk Informed ISI Inspections
ML14203A008	16 July 2014	Third Inservice Inspection Interval, Second Inservice Inspection Period 2014 Owner'S Activity Report for RFO14 Inservice Examinations
ML13261A288	6 September 2013	Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for Implementation of a Risk-Informed, Safety-Based Inservice Inspection Program Based on ASME Code Case N-716 - Response to Nrc.
ML13231A186	9 August 2013	Fourth Inservice Inspection Interval, Second Inservice Inspection Period, 2013 Owner'S Activity Report for RFO-22 Inservice Examinations	EVT-1
ML12335A288	20 November 2012	Corrected Copy of 2012 Owner'S Activity Report for Refueling Outage 13 Inservice Examinations
ML12242A236	16 August 2012	Owner'S Activity Report for Refueling Outage 13 Inservice Examinations
ML101270023	29 April 2010	American Society of Mechanical Engineers Code, Section XI, Inservice Inspection Program for Third Ten-Year Inservice Inspection Interval - 10 CFR 50.55a Request Number ISI-25, Response to NRC Request for Additional Information	Weld Overlay Dissimilar Metal Weld
ML100320052	28 January 2010	American Society of Mechanical Engineers Code, Section XI, Inservice Inspection Program for Fourth Ten-Year Inservice Inspection Interval & Associated 10 CFR 50.55a Requests - Additional Supplemental Information Relating to Relief Request 1	Internal Flooding Probabilistic Risk Assessment
ML093350523	24 November 2009	American Society of Mechanical Engineers Code, Section XI, Inservice Inspection Program for the Third Ten-Year Inservice Inspection Interval - 10 CFR 50.55a Request Number ISI-25	Dissimilar Metal Weld
ML092400149	25 August 2009	Third 10-Year Inservice Testing Program - Request for Alternative Number MSS-VR-02 Regarding Testing of Main Steam Safety Relief Valves	Time of Discovery High Radiation Area Stroke time Scaffolding
ML091950307	6 July 2009	Third Inservice Inspection Interval Third Inservice Inspection Period 2009 Owner'S Activity Report for RFO-20 Inservice Examinations
ML091830049	25 June 2009	Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for the Repair & Inservice Inspection of Control Rod Drive Stub Tubes for the License Renewal Period of Extended Operation - Response.
ML090860860	16 March 2009	Submittal of American Society of Mechanical Engineers (ASME) Code, Section XI, Inservice Inspection Program for the Fourth Ten-Year Inservice Inspection Interval and Associated 10 CFR 50.55a Requests	Non-Destructive Examination Weld Overlay Internal Flooding Hydrostatic Probabilistic Risk Assessment Nondestructive Examination VT-2 Incorporated by reference Aging Management Scram Discharge Volume Large early release frequency Liquid penetrant Through-Wall Leak Through Wall Leak Dissimilar Metal Weld
ML083230512	13 November 2008	Transmittal of Inservice Testing (IST) Program Update and Associated 10 CFR 50.55a Requests - Response to NRC Request for Additional Information	Stroke time Scram Discharge Volume Grace period
ML082671120	16 September 2008	Extension of Permanent Relief from Inservice Inspection Requirements of 10 CFR 50.55a(g) for the Volumetric Examination of Reactor Pressure Vessel Shell Circumferential Welds for the License Renewal Period of Extended Operation
ML081930965	11 July 2008	Second Inservice Inspection Interval 2008 Owners' Activity Report for Inservice Examinations
ML081840022	30 June 2008	American Society of Mechanical Engineers Code, Section XI, Inservice Inspection Program for Third Ten-Year Inservice Inspection Interval & Associated 10 CFR 50.55a Requests - Response to NRC Requests for Additional Information	Probabilistic Risk Assessment Nondestructive Examination Large early release frequency
ML081900568	30 June 2008	Inservice Testing Program Update and Associated 10 CFR 50.55a Requests for the Next Ten-Year IST Intervals	Safe Shutdown Loop seal Stroke time Hydrostatic Squib Incorporated by reference Scram Discharge Volume Excess Flow Check Valve Cold shutdown justification Exemption Request Power-Operated Valves Power Operated Valves
ML080250410	25 January 2008	American Society of Mechanical Engineers (ASME) Code, Section XI, Inservice Inspection Program for the Third Ten-Year Inservice Inspection Interval and Associated 10 CFR 50.55a Requests - Replacement of Appendix H, Relief Requests / Alterna	Nondestructive Examination VT-2 Large early release frequency
ML071370230	10 May 2007	Request for Use of Later Edition to ASME Code, Section XI for Inservice Inspection Program	Nondestructive Examination Dissimilar Metal Weld
ML062010139	13 July 2006	Owner'S Activity Report for Inservice Examinations
ML052210436	26 July 2005	Owner'S Activity Report for Inservice Examinations
ML032310438	8 August 2003	Relief, Request for Relief from Qualification Requirements for Dissimilar Metal Piping Welds	Dissimilar Metal Weld
ML032110132	23 July 2003	Submittal of Inservice Inspection Owners Activity Reports
ML030770448	6 March 2003	Inservice Inspection Relief Requests Regarding Inner Radius Examination of Class I Reactor Pressure Vessel Nozzles	EVT-1
ML003734960	18 July 2000	Inservice Inspection (ISI) Summary Report	Weld Overlay Hydrostatic Anchor Darling Nondestructive Examination VT-2 EVT-1 Liquid penetrant
ML18018B053	15 October 1999	Third Inservice Inspection Interval - Ten-Year Inservice Inspection Plan and Schedule	Weld Overlay Hydrostatic Coatings Nondestructive Examination VT-2 Incorporated by reference
ML18018B052	27 September 1999	Third Inservice Inspection Interval	Reactor Vessel Water Level Non-Destructive Examination Weld Overlay Hydrostatic Coatings Nondestructive Examination VT-2 Incorporated by reference Scram Discharge Volume Moisture barrier Earthquake EVT-1 Liquid penetrant Through Wall Leak Dissimilar Metal Weld
ML18018B013	29 July 1986	Preservice Inspection Plan for Nuclear Piping Systems and the Reactor Pressure Vessel Vol. 2	VT-2

Semantic search

Query log

Navigation menu