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AR 02182938 +, AR 02061624 +, AR 02071667 +, AR 02001233 +, AR 02081982 +, AR 02033148 +, AR 01980340 +, AR 01963361 +, AR 01711852 +, AR 00585332 +, AR 01712438 +, AR 01740921 +, AR 01716657 +, AR 01681462 +, AR 01718476 +, AR 02255986 +, AR 02269268 +, AR 02279817 +, AR 02354805 +, AR 02323757 +, AR 01693560 +, AR 02381822 +, AR 02140203 +, AR 02115822 +, AR 02013850 +, AR 02128663 +, AR 02137338 +, AR 02128751 +, AR 02388818 +, AR 02214276 +...
ML22188A086 +
10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 54 +, 10 CFR 50.12 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50 Appendix H +, 10 CFR 54.3 +, 10 CFR 54.4 +, 10 CFR 50.55a +, 10 CFR 54.3#a +, 10 CFR 54.21#a3 +, 10 CFR 54.21#c1 +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1ii +, 10 CFR 54.21#c1iii +, 10 CFR 54.21#c +, 10 CFR 54.21#ci +, 10 CFR 54.21#ciii + and 10 CFR 54.37#A +
L-2015-272, 1301103.401, Revision 0, Flaw Tolerance Evaluation of St. Lucie Surge Line Welds Using ASME Code Section XI, Appendix L, May 2015 +, L-2015-160, WCAP-17939-NP, Revision 0, Analysis of Capsule 97 Degrees from the Florida Power & Light Company St. Lucie, Unit 2, Reactor Vessel Radiation Surveillance Program, Part 3 of 3 +, L-2015-126, License Renewal One-Time Inspection of Class 1 Small Bore Piping Revised Commitments and Revised Inspection Plan +, L-2019-013, Submittal to NRC Vessels & Internals Integrity Branch of Plant-Specific Evaluation of the Core Support Barrel Spring 2018 Inspection Results +, L-2019-134, Units 1 and 2 - Quality Assurance Topical Report, Revision 22, Annual Submittal +, L-2019-130, Revised Plant-Specific Evaluation of the Core Support Barrel Spring 2018 Inspection Results +, L-2019-091, License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements +, L-2020-066, Submittal of WCAP-18452-P, Revision 1, Core Support Barrel and Core Shroud Flaw Analysis + and RA-88 +
Regulatory Guide 1.14 +, ML042670562 +, L-2017-070, Refueling Outage SL1-27 Steam Generator Tube Inspection Report +, ML17331A685 +, ML16068A245 +, ML16068A246 +, ML18071A002 +, ML17187A031 +, ML12305A254 +, ML15090A665 +, ML16145A082 +, L-2019-013, Submittal to NRC Vessels & Internals Integrity Branch of Plant-Specific Evaluation of the Core Support Barrel Spring 2018 Inspection Results +, ML19079A253 +, L-2019-064, Refueling Outage SL2-24 Steam Generator Tube Inspection Report +, ML19081A001 +, L-2019-166, Refueling Outage SL2-24 Steam Generator Tube Inspection Report RAI Response +, L-2019-130, Revised Plant-Specific Evaluation of the Core Support Barrel Spring 2018 Inspection Results +, ML19242D608 +, L-2019-091, License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements +, ML20006D152 +, ML19081A061 +, L-2020-066, Submittal of WCAP-18452-P, Revision 1, Core Support Barrel and Core Shroud Flaw Analysis +, ML20013C086 +, ML21027A226 +, ML20217L203 +, ML20175A112 +, ML19081A064 +, ML19081A058 +, ML20181A434 +, ML20181A381 +...
ER-AA-102 +, ER-AA-106 +, MA-AA-204-1000 +, ER-AA-102-1000 +, ER-AP-116 +, ER-AA-111-1000 +, ER-AA-111 +, ER-AP-121 +, ER-AA-123 +, ER-AP-116-1000 +, ER-AA-111-1001 +, FP-AA-104-1001 +, ER-AA-109 +, ER-AA-114 +, EN-AA-206 +, EN-AA-104 + and ER-AA-110-005 +
Harris B + and NRC/NRR/DNRL/NLRP +
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>.
ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +, ML22188A086 +...
July 7, 2022 +
L-2015-272, 1301103.401, Revision 0, Flaw Tolerance Evaluation of St. Lucie Surge Line Welds Using ASME Code Section XI, Appendix L, May 2015 +, L-2015-160, WCAP-17939-NP, Revision 0, Analysis of Capsule 97 Degrees from the Florida Power & Light Company St. Lucie, Unit 2, Reactor Vessel Radiation Surveillance Program, Part 3 of 3 +, L-2015-126, License Renewal One-Time Inspection of Class 1 Small Bore Piping Revised Commitments and Revised Inspection Plan +, L-2019-013, Submittal to NRC Vessels & Internals Integrity Branch of Plant-Specific Evaluation of the Core Support Barrel Spring 2018 Inspection Results +, L-2019-134, Units 1 and 2 - Quality Assurance Topical Report, Revision 22, Annual Submittal +, L-2019-130, Revised Plant-Specific Evaluation of the Core Support Barrel Spring 2018 Inspection Results +, L-2019-091, License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements + and L-2020-066, Submittal of WCAP-18452-P, Revision 1, Core Support Barrel and Core Shroud Flaw Analysis +
L-2021-142, Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021 + and L-2021-192, Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report +
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>.
01:37:37, 3 January 2025 +
NUREG/CR-4513 +, NUREG-4513 +, NUREG-1509 +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, 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-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-2191, Draft NUREG-2191 Vol 2 GALL-SLR Rev1 -12-14-24 +, NUREG-1779, Safety Evaluation Report Related to License Renewal of St. Lucie Nuclear Plant, Units 1 & 2 +, NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements + and NUREG-2192, Rev. 1, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants Final Report +
138 +
None none +, Bryce Lehman +, George Thomas +, Brian Allik +, Andrew Prinaris +, Steve Jones +, Diana Woodyatt +, Andrew Johnson +, David Nold +, Ali Rezai +, John Tsao +, Jay Collins +, Juan Lopez +, Jennifer Whitman +, David Dijamco +, Thinh Dinh +, Naeem Iqbal +, Steve Wyman +, Kent Wood +, Adakou Foli +, James Gavula +, On Yee +, Seung Min +, Carolyn Fairbanks +, Bart Fu +, Raul Hernandez +, Ata Istar +, George Wang +, Zuhan Xi +, Paul Klein +...
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 +
July 7, 2022 +
NextEra Energy + and Coffey B +
Boric Acid +, Ultimate heat sink +, Fire Barrier +, Weld Overlay +, Coatings +, Operating Basis Earthquake +, Nondestructive Examination +, VT-2 +, Functionality Assessment +, High Energy Line Break +, Aging Management +, Feedwater Heater +, Stress corrosion cracking +, Integrated leak rate test +, Moisture barrier +, License Renewal +, Subsequent License Renewal +, Subsequent License Renewal Application +, Control of Heavy Loads +, EVT-1 +, Through-Wall Leak +, Fire Protection Program +, Dissimilar Metal Weld +, Backfit +, Thermography +, Thermal fatigue +, Metamic + and Leak-Before-Break +
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WO 40628038#04 +, WO 40762995#02 +, WO 4019393701 +, WO 4054634801 +, WO 4060828907 +, WO 40361418 +, WO 40559194 +, WO 40750371 +, WO 40678939 +, WO 40677506 +, WO 40616106 +, WO 40690306#01 +, WO 40495487 +, WO 40516960 +, WO 40690308 +, WO 40706373 +, WO 40158634#01 +, WO 40458782 +, WO 40428443 +, WO 4050469301 +, WO 40609577 +, WO 4070571101 +, WO 40665085 +, WO 4004541502 +, WO 40516972 +, WO 40709203 +, WO 40356058 +, WO 40743945 +, WO 40740914 +...