Pages that link to "RNP-RA/18-0024, Report of Changes Pursuant to 10 CFR 50.59(d)(2)"
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The following pages link to RNP-RA/18-0024, Report of Changes Pursuant to 10 CFR 50.59(d)(2):
Displayed 50 items.
- RNP-RA/15-0018, Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of the Power Range Neutron Flux Channel (← links)
- RNP-RA/15-0009, Fourth 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 (Order Number EA-12-049) (← links)
- RNP-RA/14-0134, Response (90-Day) to Request for Additional Information Associated with License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 (← links)
- RNP-RA/14-0129, 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 Fukushima. (← links)
- RNP-RA/14-0126, Annual Report of Changes to or Errors Discovered in an Acceptable Loss-OF-Coolant Accident Evaluation Model Application for the Emergency Core Cooling System (← links)
- RNP-RA/14-0124, Response to Request for Additional Information Associated with Relief Request (RR)-11 for Relief from Volumetric/Surface Examination Frequency Requirements to ASME Code Case N-729-1 (← links)
- RNP-RA/14-0072, Revision of Requested Approval Date of License Amendment Request (← links)
- RNP-RA/14-0083, Third 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 (Order Number EA-12-049) (← links)
- RNP-RA/14-0092, Relief Request (RR)-11 for Relief from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-1 (← links)
- RNP-RA/14-0082, Third Six-Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051) (← links)
- RNP-RA/14-0089, Revised Reactor Operator and Senior Reactor Operator Initial Examinations (← links)
- RNP-RA/14-0077, Response to NRC Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.1.7 to Delete the Monthly Rod Position Indication Surveillance Requirements (← links)
- RNP-RA/14-0023, Reactor Operator and Senior Reactor Operator Initial Examinations (← links)
- RNP-RA/14-0061, Submittal of Snubber Examination and Testing Program (← links)
- RNP-RA/14-0049, Radiological Environmental Operating Report for 2013 (← links)
- RNP-RA/14-0040, Relief Request (RR)-10 for Expanded Applicability for Use of ASME Code Case N-532-4, Repair/Replacement Activity Documentation Requirements and Inservice Summary Report Preparation and Submission, Per 10 CFR 50.55(a)(3)(i) (← links)
- RNP-RA/14-0048, 2013 Annual Radioactive Effluent Release Report (← links)
- RNP-RA/14-0046, Report of Changes Pursuant to 10 CFR 50.59 (← links)
- RNP-RA/14-0042, Transmittal of Technical Specifications Bases Revisions (← links)
- RNP-RA/14-0021, Generic Fundamentals Examination (← links)
- RNP-RA/14-0037, Response to NRC Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.4.12, Low Temperature Overpressure Protection System (← links)
- RNP-RA/14-0013, Seismic Hazard Evaluation, 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 Near-Term Task Force Review Of. (← links)
- RNP-RA/14-0011, Revision to Response to Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident (← links)
- RNP-RA/14-0008, Second 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 (Order Number EA-12-049) (← links)
- RNP-RA/14-0028, Response to NRC Request for Additional Information Re Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals (← links)
- RNP-RA/14-0003, Response to NRC Request for Additional Information Regarding Fourth 10-Year Interval Inservice Inspection Program Plan Requests for Relief (RR)-20 (← links)
- RNP-RA/13-0123, Annual Report of Changes to or Errors Discovered in an Acceptable Loss-of-Coolant Accident Evaluation Model Application for the Emergency Core Cooling System (← links)
- RNP-RA/13-0077, License Amendment Request for Technical Specification(Ts) Change to Use NRC-Approved TSTF-491, Revision 2, Removal of Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications (← links)
- RNP-RA/13-0089, Supplemental Submittal to Correct TS Pages Re Request for Revision to Steam Generator Program Inspection Frequencies & Tube Sample Selection & Application of Permanent Alternate Repair Criteria (← links)
- RNP-RA/13-0072, Request for Site-Specific Information Related to Use of Gothic Be Withheld from Public Disclosure in Accordance with 10 CFR 2.390(a)(4) (← links)
- RNP-RA/13-0080, Response to NRC Request for Additional Information Regarding Overall Integrated Plan Submitted in Response to the Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (← links)
- RNP-RA/13-0066, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for the Pressurizer Safety Valve Indication (← links)
- RNP-RA/13-0002, License Amendment Request to Modify Technical Specification 3.1.7 to Delete the Monthly Rod Position Indication Surveillance Requirements (← links)
- RNP-RA/13-0061, Use of Gothic Computer Code for Containment Analysis (← links)
- RNP-RA/13-0053, Response to NRC Request for Additional Information Related to Pressurized Water Reactors Internals Program Plan for Aging Management of Reactor Internals (← links)
- RNP-RA/13-0043, 2012 Annual Radioactive Effluent Release Report, Annual Report January 1, 2012 - December 31, 2012 (← links)
- RNP-RA/13-0017, Response to Request for Additional Information for Review Regarding Steam Generator License Amendment Request to Revise Technical Specifications for Steam Generator Permanent Alternate Repair Criteria (← links)
- RNP-RA/12-0115, Response to Request for Additional Information for Review Regarding Deletion of the Reactor Trip on Steam Generator Water Level Low Coincident with Steam Flow/Feedwater Flow Mismatch from the Technical Specifications (← links)
- RNP-RA/12-0117, Annual Report of Changes to or Errors Discovered in an Acceptable Loss-of-Coolant Accident Evaluation Model Application for the Emergency Core Cooling System (← links)
- RNP-RA/12-0128, Response to Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident (← links)
- RNP-RA/12-0119, Supplemental Response to Request for Additional Information Related to Relief Request (RR)-07 from Immediate ASME Code Repair of Refueling Water Storage Tank Drain Valve (SI-837) for Fifth Ten-Year Inservice Inspection Program... (← links)
- RNP-RA/12-0107, Response to Request for Additional Information Related to Changes Regarding Technical Specification (TS) 3.1.4 Rod Group Alignment Limits and TS 3.1.7 Rod Position Indication (← links)
- RNP-RA/12-0066, Transmittal of Technical Specifications Bases Revisions (← links)
- RNP-RA/12-0108, Replacement Enclosure Cover Page for Request for Technical Specification (TS) Changes Regarding TS 3.1.4 Rod Group Alignment Limits and TS 3.1.7 Rod Position Indication (← links)
- RNP-RA/12-0100, Review Request for the PWR Vessel Internals Program Plan for Aging Management of Reactor Internals (← links)
- RNP-RA/12-0093, Response to NRC Request for Additional Information Related to Relief Request-2 for the Fifth 10-Year Interval Inservice Testing Program Plan (← links)
- RNP-RA/12-0065, Submittal of Updated Final Safety Analysis Report, Revision No. 24 (← links)
- RNP-RA/12-0057, License Amendment Request for Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection and Application of Permanent Alternate Repair Criteria (H*) (← links)
- RNP-RA/12-0085, Response to NRC Request for Additional Information Related to Technical Specification Change Regarding Corrections to Table 3.3.1-1 Note 1 (← links)
- RNP-RA/12-0079, Revised Response to NRC Request for Additional Information Related to Relief Request (RR)-2 for the Fifth Ten-Year Interval Inservice Testing Program Plan (← links)