Browse wiki

ACI-349 +  and ACI-318 +

IWB-2500 +  and IWC-2500 +

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

Boron +, Iron +, Nickel +, Copper +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Molybdenum +, Chloride +, Lead +, Aluminum +, Silicon +, Sulfur +, Calcium +, Chromium +  and Platinum +

BWRVIP-48 +, BWRVIP-86 +, BWRVIP-76 +, BWRVIP-139 +, BWRVIP-190 +, BWRVIP-135 +, BWRVIP-181 +, BWRVIP-48-A +, BWRVIP-100-A +, BWRVIP-329-A +  and BWRVIP-99-A +

10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50 Appendix J +, 10 CFR 54 +, 10 CFR 50.12 +, 10 CFR 50.49 +, 10 CFR 50.65 +, 10 CFR 54.3 +, 10 CFR 54.4 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 54.4a#2 +, 10 CFR 50.55a +, 10 CFR 54.4#a +, 10 CFR 54.4#a1 +, 10 CFR 54.21#a3 +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1iii +, 10 CFR 54.21#a1 +, 10 CFR 54.21#a1i +  and 10 CFR 54.21#c +

L-14-105, Notification of Impracticality for the Third 10-Year Inservice Inspection Interval +, L-05 +  and ND-3611 +

ML11122A014 +, ML052340555 +, ML021650244 +, L-14-105, Notification of Impracticality for the Third 10-Year Inservice Inspection Interval +, RBG-47860, Response to License Renewal Application NRC Request for Supplemental Information +, ML16041A090 +, ML20042B461 +, ML20363A006 +, ML20181A434 +, ML21091A187 +, L-21-282, Proposed Inservice Inspection Alternative IR-063 +, 05000254/LER-2006-004, For Quad Cities, Unit 1, Regarding Through-wall Leak in Standby Liquid Control Tank Due to the Original Construction Use of Grout with Leachable Halogens +, ML20042B60 +, ML14239A626 +  and ML21804A164 +

Vaughn Thomas +  and NRC/NRR/DNRL/NLRP +

NRC Generic Letter 16-01, Monitoring of Neutron-Absorbing Material in Spent Fuel Pools +  and NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +

ML24156A154 +, ML24156A154 +, ML24156A154 +, ML24156A154 +, ML24156A154 +, ML24156A154 +, ML24156A154 +, ML24156A154 +, ML24156A154 +, ML24156A154 +, ML24156A154 +, ML24156A154 +, ML24156A154 +, ML24156A154 +, ML24156A154 +, ML24156A154 +, ML24156A154 +, ML24156A154 +, ML24156A154 +, ML24156A154 +, ML24156A154 +, ML24156A154 +, ML24156A154 +, ML24156A154 +, ML24156A154 +  and ML24156A154 +

LR-ISG-2012-02 +, LR-ISG-2013-01 +  and LR-ISG-2015-01 +

L-14-105, Notification of Impracticality for the Third 10-Year Inservice Inspection Interval +  and L-05 +

LRA B.2.30 +, LRA B.2.37 +, LRA B.2.36 +, LRA B.2.1 +, LRA B.2.14 +, LRA B.2.24 +, LRA B.2.5 +, LRA B.2.7 +, LRA B.2.18 +, LRA B.2.21 +, LRA B.2.27 +, LRA B.2.39 +, LRA B.2.20 +, LRA B.2.25 +, LRA B.2.8 +, LRA B.2.4 +, LRA B.2.41 +, LRA B.2.42 +, LRA B.2.19 +, LRA B.2.43 +, LRA B.2.44 +, LRA B.2.22 +  and LRA B.2.6 +

NEI 94-01, License Amendment Request Supplement Pursuant to 10 CFR 50.90: Adoption of NEI 94-01, Revision 2-A, and Extension of Primary Containment Integrated Leakage Rate Test Interval to Fifteen (15) Years +  and NEI 95-10, Official Exhibit - ENT000098-00-BD01 - Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - the License Renewal Rule +

Information Notice 2013-06, Issues with Air and Water Interaction in Fire Protection Sprinkler Systems +  and Information Notice 2012-15, Use of Enclosures to Mitigate Leakage from Joints That Use A-286 Bolts +

NUMARC 93-01 +  and NUMARC 87-00 +

NUREG/CR-6260 +, NUREG/CR-5576 +, NUREG-1557, Technical Info from Industry Repts Addressing License Renewal, Presented at 970817-22 14th Intl Conference on Structural Mechanics in Reactor Technology in Lyon,France +, NUREG-2191, Draft NUREG-2191 Vol 2 GALL-SLR Rev1 -12-14-24 +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +, NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +, NUREG-2221, Supplement 1, Technical Bases for Changes in the Subsequent License Renewal Guidance Documents, NUREG-2191, Revision 1, and NUREG-2192, Revision 1 Final Report +  and NUREG-2192, Rev. 1, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants Final Report +

Nozzle:N6 +  and Nozzle:N12 +

RT +, TP-7 +, EP-113 +, TP-300 +, CP-150 +, CP-98 +, TP-204 +, TP-6 +, CP-37 +, CP-107 +, CP-113 +, CP-63 +, TP-108 +, TP-34 +, CP-67 +, SP-2100 +  and EP-113a/113b +

Regulatory Guide 1.155 +, Regulatory Guide 1.160 +, Regulatory Guide 1.190 +  and Regulatory Guide 1.99 +

Feedwater +, Service water +, Emergency Diesel Generator +, Primary containment +, HVAC +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Shield Building +, Standby Liquid Control +, Safety Relief Valve +, Control Room Envelope +  and Containment Spray +

TS-3.4.11 +  and TS-3.4.7 +

Safe Shutdown +, Boric Acid +, Non-Destructive Examination +, Grab sample +, Fire Barrier +, Internal Flooding +, Hydrostatic +, Coatings +, Zebra Mussel +, Incorporated by reference +, High Energy Line Break +, Aging Management +, Flow Accelerated Corrosion +, Microbiologically influenced corrosion +, Stress corrosion cracking +, License Renewal +, Exemption Request +, Subsequent License Renewal +, Earthquake +, Maintenance Rule Program +, Biofouling +, Through-Wall Leak +, Fire Protection Program +, Dissimilar Metal Weld +, Thermography +  and Spent fuel rack +

WO 200358401 +, WO 200727052 +, WO 200876542 +  and WO 200710364 +