Pages that link to "CP-202100550, Quality Assurance Program Internal Audit Frequency"
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The following pages link to CP-202100550, Quality Assurance Program Internal Audit Frequency:
Displayed 50 items.
- 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, 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, 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-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)
- 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)
- CP-201700120, Relief Request 2B3-1 Third Ten Year Inservice Inspection Interval from 10 CFR 50.55a Inspection Requirements Due to Geometric Limitations (← links)
- CP-201600869, Submittal of Eighteenth Refueling Outage (1RF18) Inservice Inspection Summary Report (← links)
- CP-201501100, Response to Request for Additional Information for Relief Request B-3 for the Second Ten-Year Inservice Inspection Interval Fram 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code....) (← links)
- CP-201501103, Response to Request for Additional Information for Relief Request B-11 for the Second Ten-Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code....) (← links)
- CP-201501104, Response to Request for Additional Information for Relief Requests B-15, C-2, and C-4 for the Second Ten-Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition Of. (← links)
- CP-201501101, Response to Request for Additional Information for Relief Request B-9 for the Second Ten-Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code....) (← links)
- CP-201501102, Response to Request for Additional Information for Relief Request B-10 for the Second Ten-Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME, Section...) (← links)
- CP-201500995, Compliance with NRC Order Modifying Licenses with Regard to Requirements for Mitigating Strategies for Beyond Design-Basis External Events (Order Number EA-12-049) (← links)
- CP-201500957, Core Operating Limits Report, Cycle 16, Revision 0 (← links)
- CP-201500727, Request for Enforcement Discretion Regarding Compliance with Technical Specification 3.5.2, ECCS - Operating (← links)
- CP-201500554, Response to Request for Additional Information, 2RF14 Steam Generator Tube Inservice Inspection Report (← links)
- CP-201500509, Response to Request for Additional Information for Relief Request No. 2C3-1 for the Reactor Vessel Leak-Off Flange (Third ISI Interval Start Date: August 3, 2014; Third ISI Interval End Date: August 2, 2024) (← links)
- CP-201500441, Response to Request for Additional Information, 2RF14 Steam Generator Tube Inservice Inspection Report - TAC MF5052 (← links)
- CP-201500157, Relief Request No. 2C3-1 for the Reactor Pressure Vessel Leak-Off Flange (Third ISI Interval Start Date: August 3, 2014; Third ISI Interval End Date: August 2, 2023) (← links)
- CP-201401227, Cycle 15 Core Operating Limits Report, Revision 1 (← links)
- CP-201401268, Fourteenth Refueling Outage (2RF14) Steam Generator 180 Day Report (← links)
- CP-201401035, Relief Requests Nos. B-7, B-12 and B-13 for the Second 10-Year ISI Interval (Second ISI Interval Start Date: August 3, 2004; Second ISI Interval End Date: August 2, 2014) (← links)
- CP-201400397, Core Operating Limits Report, Cycle 15 (← links)
- CP-201301361, Relief Request No. B-14 for Reactor Pressure Vessel Hot Leg Nozzle Weld Examinations (Second ISI Interval End Date: August 2, 2014) (← links)
- CP-201301238, Sixteenth Refueling Outage (1RF16) Steam Generator 180 Day Report (← links)
- CP-201300005, Submittal of Inservice Inspection Summary Report for the 13th Refueling Outage (← links)
- CP-201300003, Submittal of Relief Request No. B-2, Third 10 Year ISI Interval from 10CFR50.55a Requirements for Reactor Vessel Hot Leg Nozzle Weld Examinations (Third ISI Interval Start Date August 13, 2010) (← links)
- CP-201201386, Core Operating Limits Report, Unit 2, Cycle 14 (← links)
- CP-201200978, Relief Request No. C-2 for the Unit 1 Reactor Pressure Vessel Leak-off Flange (Third ISI Interval Start Date: August 13, 2010) (← links)