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ML080360549 +
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 +
Has query"Has query" is a predefined property that represents meta information (in form of a <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Subobject">subobject</a>) about individual queries and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 +, ML080360549 + and ML080360549 +
February 14, 2008 +
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 +
Modification date"Modification date" is a predefined property that corresponds to the date of the last modification of a subject and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
23:14:54, 14 January 2025 +
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 +
165 +
Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.
Other +
February 14, 2008 +
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 +
Audit Summary Regarding the License Renewal Application for the Wolf Creek Generating Station - AMP AMR +
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 +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.
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 +