Pages that link to "RS-16-078, Clarification to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds"
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The following pages link to RS-16-078, Clarification to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds:
Displayed 45 items.
- ML17013A605 (← links)
- ML17047A038 (← links)
- ML17178A076 (← links)
- ML16320A037 (← links)
- ML16320A036 (← links)
- ML16095A291 (redirect page) (← links)
- ML17047A038 (← links)
- ML16109A337 (← links)
- RS-18-124, Relief Request Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection Interval (← links)
- RS-16-224, Relief Request for Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection Interval (← links)
- CAC:MF8856 (← links)
- RS-16-078, Braidwood and Byron - Clarification to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove (redirect page) (← links)
- RS-16-078 (redirect page) (← links)
- RS-18-124, Relief Request Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection Interval (← links)
- RS-16-224, Relief Request for Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection Interval (← links)
- RS-16-078, Clarification to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds (← links)
- ML16320A038 (← links)
- RS-18-095, Response to Request for Additional Information Regarding Braidwood Station Fourth Lnservice Inspection Interval Relief Request 14R-03 (← links)
- RS-18-094, Response to Request for Additional Information Regarding Braidwood Station Fourth Lnservice Inspection Interval Relief Request 14R-06 (← links)
- RS-16-175, High Frequency Supplement to Seismic Hazard Screening Report,Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 the Near Term-Task Force Review of Insights from the Fukushima Dai-ichi Accident (← links)
- RS-18-041, Response to Request for Additional Information Regarding Request for Relief (I4R-07) for Extension of Examination Interval for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened ... (← links)
- RS-16-231, Revised Response to Request for Additional Information for License Amendment Request for a One-Time Extension of the Essential Service Water (SX) Train Completion Time to Support 2A SX Pump Repair (← links)
- RS-16-222, Response to Request for Additional Information Related to License Amendment Request for a One-Time Extension of the Essential Service Water (SX) Train Completion Time to Support 2A SX Pump Repair (← links)
- RS-16-218, Response to Request for Additional Information License Amendment Request for a One-Time Extension of the Essential Service Water Train Completion Time to Support 2A SX Pump Repair (← links)
- BYRON 2015-0084, Response to Request for Additional Information Regarding Steam Generator Tube Inspection Report for Refueling Outage 18 (← links)
- RS-18-083, Response to Request for Additional Information Regarding Braidwood Station Fourth Inservice Inspection Interval Relief Request 14R-05 (← links)
- RS-17-036, Response to Request for Additional Information Regarding Relief Request I4R-10 (← links)
- RS-16-259, Response to Request for Additional Information for Relief Request I4R-10: Proposed Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection Interval (← links)
- RS-16-213, Response to Request for Additional Information Regarding Relief Request 13R-17 to Extend the Reactor Pressure Vessel Inservice Inspection Interval (← links)
- RS-16-224, Relief Request for Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection Interval (← links)
- RS-16-195, Supplemental Information for the Fourth Inservice Inspection Interval Relief Request 14R-08 (← links)
- RS-16-122, Spent Fuel Pool Evaluation Supplemental Report, 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 Fukushima Dai-ichi Accident (← links)
- RS-16-112, Response to Request for Additional Information Regarding Request for a License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink. (← links)
- RS-15-329, Response to Request for Additional Information Regarding Request for a License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink. (← links)
- RS-15-319, Responds to Request for Additional Information Regarding Relief Request RP-1 Associated with the Fourth Inservice Testing Interval (← links)
- RS-15-282, Response to Request for Additional Information Regarding Request for a License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink. (← links)
- RS-15-266, Response to Request for Additional Information Regarding Request for a License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink. (← links)
- RS-16-067, Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds (← links)
- RS-16-057, Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds (← links)
- RS-16-045, Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds (← links)
- RS-19-051, Response to Request for Additional Information for the License Amendment Request to Utilize Tvel TVS-K Lead Test Assemblies (← links)
- RS-18-084, Response to Request for Additional Information Regarding Braidwood TORMIS Amendment Request (← links)
- RS-17-032, Response to Request for Additional Information Regarding the License Amendment Request to Utilize the TORMIS Computer Code Methodology (← links)
- RS-20-012, Response to Request for Additional Information Regarding Relief Request Associated with the Third Ten-Year Inservice Inspection Program Interval (← links)
- RS-20-057, Response to Request for Additional Information Regarding Emergency License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections (← links)
- RS-20-100, Response to Request for Additional Information Regarding Application for Revision to TS 5.5.9, Steam Generator (SG) Program, for a One-Time Deferral of Steam Generator Tube Inspections (← links)
- RS-20-150, Response to Request for Additional Information Related to Subsequent Exemption from Part 26 Requirements (← links)
- RS-20-147, Response to Request for Additional Information Related to Exemption from Part 26 Requirements (← links)
- RS-21-019, Response to Request for Additional Information Regarding Application for Revision to TS 5.5.9, Steam Generator (SG) Program, for a One-Time Deferral of Steam Generator Tube Inspections (← links)
- RS-21-024, Response to Request for Additional Information (RAI) Regarding Byron Station, Units 1 and 2, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition (← links)
- RS-22-072, Response to Request for Additional Information Regarding License Amendment to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink (← links)
- RS-23-038, Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly (← links)