Pages that link to "ASME Code Case N-640"
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The following pages link to ASME Code Case N-640:
Displayed 50 items.
- RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems (← links)
- LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 5, Reactor Coolant System and Connected Systems (← links)
- LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Sections 5.2.1 to 5.2-75 (← links)
- LR-N17-0034, Salem Generating Station, Units 1 & 2, Submittal of Revision 29 to Updated Final Safety Analysis Report, and Technical Specification Bases Changes and Quality Assurance Topical Report, NO-AA-10, Rev. 85 (← links)
- RS-16-248, Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Requirements Manual (← links)
- RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Requirements Manual (← links)
- NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Table 4.3-1 (Sheet 1 of 3) Through Figure 6-2.1-15 (Sheet 14 of 65) (← links)
- NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 4 - Reactor Coolant System (← links)
- NL-13-148, Browns Ferry, Unit 1, Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature Limits (BFN TS 484) (← links)
- RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 05 - Reactor Coolant System and Connected Systems (← links)
- ML101120652 (← links)
- ML101110128 (← links)
- ML101100678 (← links)
- ML100630161 (← links)
- ML093200206 (← links)
- ML090760605 (← links)
- ML090641016 (← links)
- ML090641014 (← links)
- ML090640303 (← links)
- ML081490347 (← links)
- LIC-08-0071, Transmittal of Fort Calhoun, Unit 1, Reactor Coolant System Pressure and Temperature Limits Report, Revision 4 (← links)
- ML072410389 (← links)
- ML072330414 (← links)
- ML071510549 (← links)
- ML071270018 (← links)
- ML070680173 (← links)
- ML070580236 (← links)
- NL-07-008, Proposed Changes to Indian Point, Unit 3 Technical Specifications Regarding Updated Pressure-Temperature and Low Temperature Overpressure Protection System Limits (← links)
- ML070240261 (← links)
- LIC-06-0138, Transmittal of Revision 3 of Fort Calhoun Station, Unit No. 1 (Fcs), Pressure Temperature Limits Report (PTLR) (← links)
- ML063410301 (← links)
- ML062540011 (← links)
- ML062170005 (← links)
- ML061890003 (← links)
- ML061460284 (← links)
- ML061150142 (← links)
- ML061090658 (← links)
- ML060760392 (← links)
- ML060390107 (← links)
- ML060190107 (← links)
- ML043090143 (← 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)
- ML18017A399 (← links)
- RA-18-0204, Transmittal of Technical Specification Bases (← links)
- RS-18-105, License Amendment Request to Recapture Low-Power Testing Time (← links)
- L-17-277, Pressure and Temperature Limits Reports, Revisions 8 and 9 (← links)
- HNP-16-064, Transmittal of Technical Specification Bases (← links)
- L-16-229, Submittal of Pressure and Temperature Limits Report, Revision 3 (← links)
- HNP-15-046, Transmittal of Technical Specifications Bases (← links)
- CNL-14-144, Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits (BFN TS-494) (← links)