Pages that link to "CNL-17-071, Seismic Probabilistic Risk Assessment, Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident"
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The following pages link to CNL-17-071, Seismic Probabilistic Risk Assessment, Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident:
Displayed 50 items.
- ML17181A485 (redirect page) (← links)
- ML18093A445 (← links)
- ML18156A151 (← links)
- ML18115A138 (← links)
- CNL-18-007, Seismic Probabilistic Risk Assessment Supplemental Information (← links)
- CNL-17-140, NEI 12-06, Appendix H, Revision 4, H.4.5 Path 5: GMRS ≫ 2 X SSE, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information (← links)
- ML19071A354 (← links)
- CNL-18-068, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (WBN-TS-17-24) (← links)
- ML19053A529 (← links)
- ML19169A359 (← links)
- CNL-19-065, Partial Response to NRC Request for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (← links)
- ML19248C797 (← links)
- LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors (← links)
- ML19343A019 (← links)
- NMP2L2716, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors (← links)
- ML20028F733 (← links)
- ML19330D909 (← links)
- RS-20-052, Application to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Extended Completed Times-RITSTF Initiative 4b (← links)
- ML20076A194 (← links)
- RS-20-133, Response to Request for Additional Information Re License Amendment Request to Renewed Facility Operating Licenses to Adopt 10 CFR 50.69 (← links)
- RS-20-139, Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-505, Revision 2, and 10 CFR 50.69 (← links)
- ML20322A160 (← links)
- RA-20-0311, License Amendment Request to Revise the 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process. (← links)
- ML21070A412 (← links)
- ML21081A040 (← links)
- ML21082A422 (← links)
- 2CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (← links)
- 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (← links)
- JAFP-21-0069, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors (← links)
- JAFP-21-0070, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b (← links)
- W3F1-2021-0050, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt (← links)
- ML21349B364 (← links)
- ML21344A126 (← links)
- W3F1-2022-0009, Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors (← links)
- NMP1L3484, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Reatment of Structures, Systems and Components for Nuclear Power Reactors (← links)
- SVP-22-057, Response to Apparent Violation EA-22-062 and Preliminary White Finding Regarding the Failure of One Electromatic Relief Valve (← links)
- RA-18-0090, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors (← links)
- RS-23-060, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (← links)
- RS-23-059, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (← links)
- RA-23-0122, License Amendment Request to Revise the 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to . (← links)
- ML23192A447 (← links)
- RA-23-0279, Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power (← links)
- CP-202300575, (Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 2 (← links)
- ML15055A543 (← links)
- TAC:MF3769 (← links)
- ML18155A487 (← links)
- CNL-18-113, Response to Request for Additional Information Regarding Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) . (← links)
- CNL-18-018, Supplement to Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) (← links)
- CNL-17-071, Watts Bar, Units 1 and 2 - Seismic Probabilistic Risk Assessment, Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Ac (redirect page) (← links)
- CNL-17-071 (redirect page) (← links)
- CNL-15-232, Attachment 1, CE-15-588-NP-Attachment, Rev. 1 and Attachment 3, CE-15-611-NP-Attachment Regarding Proposed Response to NRC RAIs Nos. 1, 2, 3, and 4 Regarding LAR for Increasing the Maximum Number of Tpbars in Watts Bar, Unit 1. (Non-Propr (← links)
- CNL-18-128, Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Use of Voltage-Based Alternate Repair Criteria in Accordance with Generic Letter 95-05 (391-WBN2-TS-17-30) (← links)
- CNL-18-104, Submittal of Revised Response to Request for Additional Information Regarding Application to Modify Plant Technical Specifications to Extend Surveillance Requirements 3.3.1.5, 3.3.2.2 and 3.3.6.2 Specified Intervals (← links)
- CNL-18-102, Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications to Extend Surveillance Requirement 3.3.1.5, 3.3.2.2, and 3.3.6.2 Specified ... (← links)
- CNL-18-012, Response to Request for Additional Information and Revision 1 to Technical Specification Change - Reactor Coolant Temperature Indicator Inoperable - Exigent Amendment (391-WBN-TS-2018-01) (← links)
- CNL-17-066, Response to Request for Additional Information Regarding License Amendment Request for One-Time Extension of Technical Specification Surveillance Requirements Group 2 (LAR Encl. 1 Attachments 5, 6, 7, 9, 12, 13, 14, 15, 16, and 17) (← links)
- CNL-17-062, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications Regarding Ice Condenser Containment Ice Mass Requirements (← links)
- CNL-17-029, Response to Request for Additional Information Regarding License Amendment Request for a One-Time Extension of Technical Specification Surveillance Requirements for AC Sources (← links)
- CNL-16-047, Response to Request for Additional Information Regarding Request to Use F* Steam Generator Alternate Repair Criteria (← links)
- CNL-16-038, Application to Revise Technical Specification 4.2.1, Fuel Assemblies and Radioactive Waste System Design Basis Source Term Supplement to Response to NRC Request for Additional Information (← links)
- CNL-16-027, Response to Request for Additional Information Regarding Request for Relief ISPT-02 (← links)
- CNL-15-216, Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) (TAC No. MF6050) - Response to NRC Request for Additional Information - Radiation Protection and Consequence Branch (← links)
- CNL-16-030, Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) (TAC No. MF6050) - Supplement to Response to NRC Request for Additional Information - Radiation Protection and Consequence Branch (← links)
- CNL-15-263, Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory (← links)
- CNL-15-206, Response to Follow-Up Question Regarding Submittal of Electromagnetic Interference (EMI) Survey Results (← links)
- CNL-15-220, Response to Request for Additional Information - Developmental Revision I Technical Specification Section 3.8 - Diesel Generator Batteries (← links)
- CNL-15-179, Response to Request for Additional Information Regarding Request for Relief WBN-2/PSI-3 for Inaccessible Steam Generator Lower Shell-to-Cone Weld SG-4B-5-2 (← links)
- CNL-15-192, Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Response to NRC Request for Additional Information - Radiation Protection and Consequence Branch (← links)
- CNL-15-196, Response to Request for Additional Information Regarding Relief Request IST-RR-2 (← links)
- CNL-15-205, Response to Additional Question Regarding Request for Relief WBN-2/PSI-3 for Inaccessible Steam Generator Lower Shell-to-Cone Weld SG-4B-5-2 (← links)
- CNL-15-204, Response to NRC Question Regarding the Revised Containment Analysis, Including Enclosure 3, WCAP-17834-NP, Revision 2, Wcobra/Trac Long Term LOCA M&E and Containment Integrity Analysis and Enclosure 4, Affidavit (← links)
- CNL-15-172, Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Response to NRC Request for Additional Information - Reactor Systems Branch (← links)
- CNL-15-094, Responses to Requests for Additional Information - Developmental Revision I Technical Specification Section 3.8 (← links)
- CNL-15-133, Response to Request for Additional Information Related to Technical Specification 3.8.1 Regarding Diesel Generator Steady State Frequency (WBN-TS-13-08) (← links)
- CNL-15-078, Response to NRC Request for Additional Information Related to Application to Modify Technical Specifications Regarding AC Sources - Operating (TS-WBN-13-02) (← links)
- L-11-011, Transmittal of Response to NRC Bulletin 2011-01, Mitigating Strategies. (← links)
- CNL-18-061, Response to NRC Request for Supplemental Information Related to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (← links)
- CNL-16-195, Spent Fuel Pool Evaluation Supplemental Report - Response to NRC Request for Information, Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (← links)
- CNL-16-187, Response to Request for Additional Information Regarding Request to Revise Technical Specifications for Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating (← links)
- CNL-16-137, Response to Request for Additional Information Regarding Request to Revise Technical Specifications for Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources Operating . (← links)
- CNL-14-196, Response to Request for Additional Information on Radiological Emergency Plan (← links)
- CNL-14-141, Response to Request for Additional Information on the Radiological Emergency Plan (← links)
- CNL-18-121, Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19) (← links)
- CNL-18-058, Supplement to Application to Revise Watts Bar Nuclear Plant Unit 2 - License Condition 2.C(4) PAD4TCD (391-WBN-TS-18-03) (← links)
- CNL-17-108, Response to Request for Additional Information Regarding Request to Modify Technical Specification 3.3.1, Reactor Protection System Instrumentation (← links)
- CNL-17-020, Response to RAI Regarding License Amendment Request for One-Time Extension of Technical Specification Surveillance Requirements Group 1 - LAR Attachments 8, 10, and 11 (← links)
- CNL-16-090, Revised Response to Request for Additional Information Regarding Request to Use F* Steam Generator Alternate Repair Criteria (← links)
- CNL-15-153, Response to Request for Additional Information Related to Application to Revise Technical Specifications for Component Cooling Water and Essential Raw Cooling Water to Support Dual Unit Operation (← links)
- CNL-18-116, Response to Request for Additional Information Regarding the Application to Revise Watts Bar Nuclear Plant Unit 2 - License Condition 2.C(4) PAD4TCD (391-WBN-TS-18-03) (← links)
- CNL-17-093, Revised Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (ABGTS) (← links)
- CNL-17-091, Response to Request for Additional Information Regarding Request for Approval of a Relief from the ASME Section XI Coverage Examinations for Preservice Inspection (PSI) - Number WBN-2/PSI-1, Revision 1, and Submittal of the Wbn.. (← links)
- CNL-19-033, Revised Response to Request for Additional Information Regarding Application to Modify Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19) (← links)