Browse wiki

ACI-318 +, ACI-349 +  and ACI-201 +

ASME Section XI +, ASME Section III +, ASME Section IX +, ASME Section V +  and ASME Section VIII +

Boron +, Iron +, Nickel +, Copper +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Molybdenum +, Chloride +, Lead +, Lithium +, Aluminum +, Sulfur +, Calcium +  and Zinc +

10 CFR 50 Appendix R +, 10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 54 +, 10 CFR 50.49 +, 10 CFR 50 Appendix G +, 10 CFR 54.3 +, 10 CFR 50.54 +, 10 CFR 50.55a +, 10 CFR 54.4#a2 +, 10 CFR 54.4#a3 +, 10 CFR 54.4#a1 +, 10 CFR 50.63#a1 +  and 10 CFR 50 Appendix J#B +

WO 01 +, WO 95 +, WO 98 +, WO 99 +, WM 89-0015 +, WO 04-0039, 60-Day Response to NRC Bulletin 2004-01, 'Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors. +, WM 04-0004, Response to NRC Order, Issuance of First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors +, WM 04-0002, 60-Day Report for NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity. +, WM 04-0001, Report for NRC Order EA-03-009, Issuance of Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors +, WM 03-0044, Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations & Reactor Coolant Pressure Boundary Integrity +  and WM 06-0051, Day Report for NRC Order EA-03-009, Issuance of First Revised Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors +

ML010660292 +  and ML022690375 +

FP-452 +, FP-600 +, FP-400A +, FP-404A +  and FP-404B +

NRC Generic Letter 88-13, Operator Licensing Examinations +  and NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +

ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +  and ML080360549 +

3.819444e-4 d (0.00917 hours, 5.456349e-5 weeks, 1.25565e-5 months)  +  and 0.00116 d (0.0278 hours, 1.653439e-4 weeks, 3.805e-5 months)  +

LRA B.2.1.10 +, LRA B.2.1.9 +, LRA B.2.1.21 +, LRA B.2.1.30 +, LRA B.2.1.22 +, LRA B.2.1.8 +, LRA B.2.1.6 +, LRA B.2.1.4 +, LRA B.3.1 +  and LRA B.3.2 +

05000482/LER-2006-003, For Wolf Creek Generating Station Regarding Indications Discovered on Pressurizer During Preplanned In-service Inspections +, ML072820307 +, ET 06-0035, Relaxation Request from First Revised NRC Order EA-03-009 Regarding Requirements for Nondestructive Examination of Nozzles Below J-Groove +, ET 07-0038, License Renewal Application, Amendment 3 +  and ET 07-0020, Response to NRC Requests for Additional Information Related to Wolf Creek Generating Station License Renewal Application +

NEI 97-06, Steam Generator Conditioning Monitoring Report +  and NEI 03-08, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program (MRP) 2019-008, Materials Reliability Program: Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants . +

NFPA 25 +  and NFPA 1962 +

NRC Bulletin 04-01 +, NRC Bulletin 02-01 +, NRC Bulletin 88-09 +, NRC Bulletin 03-02 +  and NRC Bulletin 82-02 +

Information Notice 88-04 +, Information Notice 94-28 +, Information Notice 88-56 +, Information Notice 96-09 +  and Information Notice 91-19 +

NUREG/CR-6260 +, NUREG-1843, Supp 1, Safety Evaluation Report Related to the License Renewal of the Browns Ferry Nuclear Plant, Units 1, 2 & 3 +, NUREG-1856, Safety Evaluation Report Related to the License Renewal of the Brunswick Steam Electric Plant, Units 1 and 2, Section 3 - Aging Management Review Results Through End +, NUREG-1831 +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-1552, Informs That During 454th Meeting of ACRS on 980708-10, Representatives of NRC Staff Met W/Licensee to Discuss Suppl 1 to NUREG-1552 +, NUREG-1839, (2:2) Section 3 - End, Safety Evaluation Report Related to the License Renewal of the Point Beach Nuclear Plant, Units 1 & 2 +, NUREG-1838, V2, Safety Evaluation Report Related to the License Renewal of the Millstone Power Station, Units 2 and 3 +, NUREG-1787, Safety Evaluation Report Related to the License Renewal of the Virgil C. Summer Nuclear Station +, NUREG-1785, (2:2) Page 3-337 - End, Safety Evaluation Report Related to the License Renewal of H. B. Robinson Steam Electric Plant, Unit 2 +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +  and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +

4.16kV +  and 345kV +

ES +, RT +  and Emergency Plan +

Regulatory Guide 1.127 +, Regulatory Guide 1.65 +, Regulatory Guide 1.54 +, Regulatory Guide 1.43 +  and Regulatory Guide 1.85 +

16F-001 +, 3A-53 +, 29E-001 +, 23M-007 +, 16F-002 +, 28A-001 +, 23L-001 +, 23H-002 +, 16C-005 +, 24D-003 +, 24H-003 +, M711Q-02 +, M711Q-03 +, M711Q-04 +, M711Q-06 +, M712Q-04 +, M713Q-01 +  and 02B-001 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Auxiliary Feedwater +, Primary containment +, Main Turbine +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Standby Gas Treatment System +, Fuel Pool Cooling and Cleanup +, Circulating Water System +, Emergency Core Cooling System +, Moisture Separator Reheater +, Control Rod +, Auxiliary Feed Water +, Main Steam +, Containment Spray +  and Extraction steam +

Safe Shutdown +, Boric Acid +, Ultimate heat sink +, Fire Barrier +, Hydrostatic +, Coatings +, Nondestructive Examination +, VT-2 +, Finite Element Analysis +, Aging Management +, Local Leak Rate Testing +, Flow Accelerated Corrosion +, Feedwater Heater +, Stress corrosion cracking +, Eddy Current Testing +, Moisture barrier +, License Renewal +, Biofouling +, Through-Wall Leak +, Fire Protection Program +, Eddy Current Test +  and Thermography +

WCAP-12866 +, WCAP-14574-A +, WCAP-15338 +, WCAP-15338-A +  and WCAP-15388 +

WM 89-0015 +, WM 04-0004, Response to NRC Order, Issuance of First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors +, WM 04-0002, 60-Day Report for NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity. +, WM 04-0001, Report for NRC Order EA-03-009, Issuance of Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors +, WM 03-0044, Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations & Reactor Coolant Pressure Boundary Integrity +  and WM 06-0051, Day Report for NRC Order EA-03-009, Issuance of First Revised Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors +

WO 01 +, WO 95 +, WO 98 +, WO 99 +  and WO 04-0039, 60-Day Response to NRC Bulletin 2004-01, 'Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors. +

WCAP-12866 +, WCAP-14574-A +, WCAP-15338 +, WCAP-15338-A +  and WCAP-15388 +