Pages that link to "FOR"

The following pages link to FOR:

Displayed 50 items.

• RS-16-012, Peach Bottom, Units 2 and 3 - Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi ‎ (← links)
• CP-201501100, Comanche Peak, Unit 2 - Response to Request for Additional Information for Relief Request B-3 for the Second Ten-Year Inservice Inspection Interval Fram 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ‎ (← links)
• CP-201501101, Comanche Peak, Unit 2 - Response to Request for Additional Information for Relief Request B-9 for the Second Ten-Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ‎ (← links)
• CP-201500781, Comanche Peak, Unit 2 - Relief Request C-4, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section Xi, 2000 Addenda Second Interval Start ‎ (← links)
• CP-201500780, Comanche Peak, Unit 2 - Relief Request C-2, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section Xi, 2000 Addenda Second Interval Start ‎ (← links)
• CP-201500776, Comanche Peak, Unit 2 - Relief Request B-9, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section Xi, 2000 Addenda Second Interval Start ‎ (← links)
• CP-201500775, Comanche Peak, Unit 2 - Relief Request B-3, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section Xi, 2000 Addenda Second Interval Start ‎ (← links)
• CP-201500685, Comanche Peak - Response to Request for Additional Information for Relief Request 2A3-1, Unit 2, Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section Xi Examination Requirements for ‎ (← links)
• RS-15-185, Dresden and LaSalle County - Supplemental Information Regarding Seismic Hazard Risk Evaluation and Seismic Hazard Prioritization Results - Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of ‎ (← links)
• CNS-15-035, Catawba, Unit 2 - Notification of Full Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and with Order EA-12-051, Order to Modify with ‎ (← links)
• NRC 2015-0004, Point Beach, Units 1 and 2 - LAR 266 to Revise Technical Specifications to Adopt TSTF-51 0, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement ‎ (← links)
• MNS-15-002, McGuire, Units 1 & 2, Response to August 28, 2014, & October 27, 2014, NRC Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program (TAC Nos. MF2934 and ‎ (← links)
• NL-14-210, Browns Ferry Nuclear Plant - Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the ‎ (← links)
• RS-14-301, Three Mile Island, Unit 1 - Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the ‎ (← links)
• RS-14-298, LaSalle County, Units 1 & 2 - Expedited Seismic Evaluation Process Report Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi ‎ (← links)
• L-2014-274, St. Lucie, Units 1 and 2 - Third Overall Integrated Plan Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order ‎ (← links)
• BVY 14-011, Vermont Yankee, Revision to Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from ‎ (← links)
• NL-13-123, Tennessee Valley Authority - Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding the Browns Ferry Nuclear Plant Seismic Walkdown Results of Recommendation 2.3 of the Near-Term ‎ (← links)
• NL-13-125, Response to NRC Request for Additional Information Related to Overall Integrated Plan in Response to the Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ‎ (← links)
• GNRO-2012/00140, Grand Gulf Nuclear Station, Unit No.1 - Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review ‎ (← links)
• RS-12-168, Dresden, Units 2 & 3, Exelon Generation Co., Llc'S 180-day Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi ‎ (← links)
• RC-12-0082, Virgil C. Summer, Unit 1 - 90-Day Response to Emergency Preparedness Information Request by NRC for Information Pursuant to 10CFR50.54(f) Recommendations 2.1, 2.3 and 9.3 of Near Term Task Force Review of Insights from Fukushima Dai-ichi ‎ (← links)
• ULNRC-05870, Callaway, Unit 1, Ameren Missouri Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Walkdown Procedure in Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi ‎ (← links)
• CP-201200476, Comanche Peak, Units 1 and 2, 60-Day Response to NRC Letter, Request for Information Pursuant to 10CFR50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3 of the Near-Term Task Force Review of Insights from Fukushima Dai-Ichi Accident, ‎ (← links)
• ULNRC-05862, Callaway Plant Unit 1, Ameren Missouri 60-Day Response to NRC Letter,Request for Information Pursuant to Title 10 of Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of ‎ (← links)
• RS-11-050, Braidwood, Units 1 and 2 - Third 10-Year Inservice Inspection Interval Relief Request I3R-08, Alternative Requirements to ASME Section Xi Appendix Vii (Supplements 2 and 10), Examinations of Class 1 Pressure Retaining Welds Conducted from ‎ (← links)
• L-2010-205, Turkey Point, Unit 4 - Responses to Nrc'S Request for Additional Information Dated Feb. 18, 2010 Re Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water ‎ (← links)
• RS-10-008, Clinton Power Station, Unit 1, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, ‎ (← links)
• HNP-09-086, Shearon Harris, Unit 1 - Second Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-based Standard for Fire Protection for Light Water ‎ (← links)
• CP-200800123, Comanche Peak - Supplement to License Amendment Request (LAR) 07-003 Response to Request for Additional Information Related to LAR Associated with Methodology Used to Establish Core Operating Limits and LAR 07-004 Revision to Operating ‎ (← links)
• LR-N07-0171, Pseg Nuclear LLC, Request for Withholding Information from Public Disclosure for Hope Creek Generating Station Regarding Letter, Dated August 3, 2007, Subject: Response to Request for Additional Information Request for License Amendment ‎ (← links)
• GNRO-2007/00009, Grand Gulf, Unit 1, License Amendment Request, Application for Technical Specifications (TS) Change Regarding Mode Change Limitations (TSTF-359) Using the Consolidated Line Item Improvement Process (Cliip), and Correct Example 1.4-1 ‎ (← links)
• LIC-06-0087, Fort Calhoun, Unit 1, Revised License Amendment Request, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process and Deletion of Sleeving as a SGT ‎ (← links)
• HNP-06-080, Shearon Harris Nuclear Power Plant, Unit, 60-Day Response to First Revised NRC Order EA-03-009, Issuance of First Revised NRC Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized ‎ (← links)
• NG-06-0338, Duane Arnold - Technical Specification Request: Adoption of TSTF-372, Rev. 4, Application for Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using Consolidated Line Item Improvement Process. Affected TS: ‎ (← links)
• PLA-7570, Susquehanna Steam Electric Station, Eighth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (EA-12-049), ‎ (← links)
• PLA-6852, Susquehanna - 60 Day Response to NRC Letter, Request for Information Pursuant to Title 10 of Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, & 9.3. of Near-Term Task Force Review of Insights from Fukushima Dai-Ichi ‎ (← links)
• L-09-072, Davis-Besse, Unit 1 - License Amendment Request to Incorporate the Use of Alternate Methodologies for Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves and Request for Exemption from Certain Requirements Contained in ‎ (← links)
• CNL-17-107, Browns Ferry, Units 1, 2, and 3 - Ninth Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events(Order No. ‎ (← links)
• CNL-15-132, Browns Ferry, Units 1, 2, and 3 - Second Six-Month Status Report in Response to the June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ‎ (← links)
• NL-15-059, Indian Point, Unit 3 - Notification of Full Compliance with Order EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and Order EA-12-051 Modifying Licenses with ‎ (← links)
• CNL-14-233, Watts Bar, Units 1 & 2 - Compliance Letter & Final Integrated Plan in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order ‎ (← links)
• CNL-14-010, Response to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application, 3.0.3-1 (Requests 3b, -3a, 4b, 6b); B.1.34-8; B.1.34-9; A.1-2; Tables 3.3.1, 3.3.2-11, and ‎ (← links)
• L-16-308, Request for an Amendment to Revise Technical Specification 3.3.1. Reactor Protection System ≪Rps) Instrumentation. ‎ (← links)
• L-MT-16-034, Monticello Nuclear Generating Plant: Fourth Six-Month Status Report in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ‎ (← links)
• NL-16-014, Response to Request for Additional Information Regarding IP2-ISI-RR-19 for Relief from System Test Requirements for Large Bore(≫ 1 Inch), ASME Code Class 1 Reactor Coolant Pressure Boundary (Rcpb), Process, Drain, Test, And.. ‎ (← links)
• ONS-2014-059, Response to NRC Request for Additional Information (RAI) Related to the MRP-227-A Applicant/Licensee Action Item 7 Analysis Supporting the Reactor Vessel Internals Inspection Plan Amendment Request [ANP-3267Q1NP (R1)] ‎ (← links)
• NRC 2017-0040, Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Appendix H, Section H.4.4, Path 4: GMRS ≪ 2X SSE ‎ (← links)
• L-MT-08-061, Monticello, Response to 09/26/2008, Request for Additional Information for License Amendment Request: Revision to the Allowable Value and Channel Calibration Surveillance Interval for the Recirculation Riser Differential Pressure - High ‎ (← links)
• LR-N07-0171, PSEG Nuclear LLC, Request for Withholding Information from Public Disclosure for Hope Creek Generating Station Regarding Letter, Dated August 3, 2007, Subject: Response to Request for Additional Information Request for License Amendment ‎ (← links)