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ML19268A123 +
10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.65 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 54.4 +, 10 CFR 54.29 +, 10 CFR 50.55a +, 10 CFR 54.4#a1 +, 10 CFR 50.49#f +, 10 CFR 50.61#c +, 10 CFR 54.21#d +, 10 CFR 54.21#1 +, 10 CFR 54.21#c1 +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1ii +, 10 CFR 54.21#c1iii + and 10 CFR 54.21#c +
ML17032A516 +, W3F1-2016-0071, Responses to Request for Additional Information Set 4 Regarding the License Renewal Application +, ML17054D239 +, W3F1-2017-0015, Responses to Request for Additional Information Set 13 Regarding the License Renewal Application +, W3F1-2017-0026, Responses to Request for Additional Information Set 15 Regarding the License Renewal Application +, ML16088A324 +, W3F1-2017-0023, Responses to Request for Additional Information Set 14 Regarding the License Renewal Application +, W3F1-2017-0039, Responses to Request for Additional Information Set 17 Regarding the License Renewal Application +, W3F1-2016-0074, Responses to Request for Additional Information Set 5 Regarding the License Renewal Application +, ML16315A235 +, W3F1-2016-0070, Responses to Request for Additional Information Set 3 Regarding the License Renewal Application +, W3F1-2017-0065, License Amendment Request for Use of RAPTOR-M3G Code for Neutron Fluence Calculations +, ML18228A668 +, ML16287A675 +, ML17016A027 + and ML16342A491 +
NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements + and NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +
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>.
ML19268A123 +, ML19268A123 +, ML19268A123 +, ML19268A123 +, ML19268A123 +, ML19268A123 +, ML19268A123 +, ML19268A123 +, ML19268A123 + and ML19268A123 +
September 11, 2019 +
LRA B.1.24 +, LRA B.1.28 +, LRA B.1.25 +, LRA B.1.23 +, LRA B.1.18 +, LRA B.1.29 +, LRA B.1.20 +, LRA B.1.26 +, LRA B.1.30 +, LRA B.1.3 +, LRA B.1.4 +, LRA B.1.35 + and LRA B.1.39 +
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>.
12:16:59, 3 January 2025 +
NEI 97-06, Steam Generator Conditioning Monitoring Report +, 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 . + and 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 +
NUREG/CR-5704 +, NUREG/CR-6260 +, NUREG/CR-6583 +, NUREG/CR-6031 +, 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-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-1339, Summarizes Resolution of GI 29 Bolting Degradation or Failure in Nuclear Power Plants +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, 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 +
70 +
Request +
W3F1-2017-0002 +, 3A3-S +, 3AB3-S +, 3B3-S +, 3A31-S +, 3AB31-S +, 3B31-S +, W3F1-2016-0063 +, W3F1-2016-0069 +, W3F1-2016-0071, Responses to Request for Additional Information Set 4 Regarding the License Renewal Application +, W3F1-2017-0015, Responses to Request for Additional Information Set 13 Regarding the License Renewal Application +, W3F1-2017-0026, Responses to Request for Additional Information Set 15 Regarding the License Renewal Application +, W3F1-2017-0023, Responses to Request for Additional Information Set 14 Regarding the License Renewal Application +, W3F1-2017-0039, Responses to Request for Additional Information Set 17 Regarding the License Renewal Application +, W3F1-2016-0074, Responses to Request for Additional Information Set 5 Regarding the License Renewal Application +, W3F1-2016-0070, Responses to Request for Additional Information Set 3 Regarding the License Renewal Application +, W3F1-2016-0075, Responses to Request for Additional Information Set 6 Regarding the License Renewal Application +, W3F1-2016-0012, License Renewal Application Waterford Steam Electric Station, Unit 3 (Waterford 3) (Part 9 of 9) +, W3F1-2017-0065, License Amendment Request for Use of RAPTOR-M3G Code for Neutron Fluence Calculations +, W3F1-2013-0070, Submittal of Reactor Vessel Internals Aging Management Program Consistent with MRP-227-A + and W3F1-2019-0064, Submittal of Revision 311 to Final Safety Analysis Report +
September 11, 2019 +
TS-3.4.8.1 + and TS-4.4.8.1 +
Boric Acid +, Non-Destructive Examination +, Fire Barrier +, Weld Overlay +, Coatings +, High Energy Line Break +, Aging Management +, Foreign Material Exclusion +, Stress corrosion cracking +, Moisture barrier +, License Renewal +, Earthquake +, Control of Heavy Loads +, Biofouling +, Fire Protection Program +, Backfit +, Power Uprate +, Thermography +, Spent fuel rack +, Leak-Before-Break + and Leak Before Break +
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