Pages that link to "CP-202200075, Third Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections"
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The following pages link to CP-202200075, Third Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections:
Displayed 50 items.
- ML17074A494 (← links)
- ML16351A200 (← links)
- ML15191A164 (← links)
- ML15191A163 (← links)
- ML14063A281 (← links)
- ML13071A391 (← links)
- ML13043A039 (← links)
- ML11237A127 (← links)
- ML101540314 (← links)
- ML092950551 (← links)
- ML091670154 (← links)
- ML082321278 (← links)
- ML073400047 (← links)
- CP-201300480, Comanche Peak, Unit 1, Submittal of Cycle 17 Core Operating Limits Report, Revision 0 (← links)
- CP-201300040, Comanche Peak, Units 1 and 2 - Transmittal of Year 2012 Radiological Environmental Operating Report (← links)
- CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67 (← links)
- CP-201300130, Comanche Peak, Units 1 & 2, Transmittal of Electronic Licensing Basis Documents Including Certified FSAR Amendments 105 (← links)
- CP-201201258, Comanche Peak Nuclear Power Plant - Spent Fuel Pool Criticality Analysis (← links)
- CP-201200347, Comanche Peak, Units 1 and 2, Transmittal of Year 2011 Radioactive Effluent Release Report (← links)
- CP-201200034, Comanche Peak, Units 1 and 2, Submittal of the Annual Non-Radiological Environmental Operating Report for 2011 (← links)
- CP-201100770, Letter to NRC Luminant Generation Company LLC Request for Approval of Secure Voice Communication (← links)
- CP-201101065, Comanche Peak Units 1 & 2 Final Safety Analysis Report (Fsar), Amendment 104, Technical Specifications Bases (← links)
- CP-201101065, Comanche Peak Units 1 & 2, Transmittal of Electronic Licensing Basis Documents Including Certified FSAR Amendment 104 (← links)
- CP-201100170, Comanche Peak - Guarantees of Payment of Deferred Premiums (← links)
- CP-200901403, Comanche Peak - Supplement to Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (← links)
- CP-200900748, Comanche Peak - License Amendment Request 09-007, Model D5 Steam Generator Alternate Repair Criteria (← links)
- CP-200900568, Comanche Park Steam Electric Station - Transmittal of Year 2008 Radiological Environmental Operating Report (← links)
- CP-200900615, Comanche Peak, Units 1 and 2, Transmittal of Year 2008 Radioactive Effluent Release Report (← links)
- CP-200801606, Comanche Peak - Supplement to Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, Cover Letter (← links)
- CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2 (← links)
- CP-200800612, Commanche Peak, Units 1 & 2 - Transmittal of Revised Pressure and Temperature Limits Report (← links)
- CP-200800276, Commanche Peak, Transmittal of Second-Half 2007 Fitness-for-Duty Program Performance Data (← links)
- CP-200800053, Submittal of Annual Report of Changes in Peak Cladding Temperature for Comanche Peak Steam Electric Station (CPNPP) Units 1 and 2 (← links)
- CP-201701010, Special Report 1-SR-17-001-00 for Comanche Peak Nuclear Power Plant, Unit 1 Regarding Inoperable Post Accident Monitoring Instrument Report (← links)
- CP-201301274, Revision of Commitment Number 4457005 Related to Comanche Peak Nuclear Power Plant, License Amendment Request 12-007, Revision to Technical Specification 3.8.1, AC Sources-Operating, for Two, 14-Day Completion Times for Offsite Circuits (← links)
- ML070710110 (← links)
- ML070320827 (← links)
- ML062440420 (← links)
- ML061160064 (← links)
- ML060900019 (← links)
- ML060750452 (← links)
- ML053620367 (← links)
- ML053570277 (← links)
- CP-201301109, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident - 1.5 Year Response for CEUS Sit (← links)
- CP-200901227, Revision to Request for Relief to Extend the Unit 1 and 2 in Service Inspection Interval for the Reactor Vessel Weld Examination and Withdrawal of License Amendment Request 09-004 to Add License Condition for Submittal of ISI Informatio (← links)
- CP-201800652, Special Report 1-SR-18-001-00, Inoperable Post Accident Monitoring Instrumentation Report (← links)
- CP-201800215, Submittal of Nineteenth Refueling Outage (1RF19) Steam Generator 180 Day Report (← links)
- CP-201700977, Core Operating Limits Report, Rev. 1 (← links)
- CP-201700805, Sixteenth Refueling Outage (2RF16) Steam Generator 180 Day Report (← links)
- CP-201700308, Core Operating Limits Report for Cycle 17, Prepared Per Technical Specification 5.6.5 (← links)