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ML061920452 +
10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.49 +, 10 CFR 50.65 +, 10 CFR 54.21 +, 10 CFR 50.55a +, 10 CFR 54.4#a2 +, 10 CFR 54.4#a3 +, 10 CFR 54.4#a1 +, 10 CFR 50.49#e +, 10 CFR 50.54#a2 +, 10 CFR 50.54#a1 +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1iii +, 10 CFR 54.21#a1i +, 10 CFR 54.21#c +, 10 CFR 54.21#a1ii +, 10 CFR 50.46#b5 +, 10 CFR 50.55#a + and 10 CFR 54#a1 +
NRC Generic Letter 80-95, Generic Activity A-10 +, NRC Generic Letter 87-05, Request for Additional Information Assessment of Licensee Measures to Mitigate and/or Identify Potential Degradation of Mark I Drywells +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment + and NRC Generic Letter 98-04, Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment +
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>.
ML061920452 +, ML061920452 +, ML061920452 +, ML061920452 +, ML061920452 +, ML061920452 +, ML061920452 +, ML061920452 +, ML061920452 +, ML061920452 +, ML061920452 + and ML061920452 +
July 11, 2006 +
LRA B.1.28 +, LRA B.1.1 +, LRA B.1.21 +, LRA B.1.25 +, LRA B.1.23 +, LRA B.1.18 +, LRA B.1.19 +, LRA B.1.7 +, LRA B.1.20 +, LRA B.1.26 +, LRA B.1.16 +, LRA B.1.2 +, LRA B.1.10 +, LRA B.1.17 +, LRA B.1.9 +, LRA B.1.30.2 +, LRA B.1.12.1 +, LRA B.1.12.2 +, LRA B.1.30.3 +, LRA B.1.30.1 + and LRA B.1.20.3 +
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>.
13:05:41, 15 January 2025 +
NEI 96-03 +, NEI 95-10, Official Exhibit - ENT000098-00-BD01 - Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - the License Renewal Rule + 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-6260 +, NUREG-1831 +, NUREG-6260 +, NUREG-1833 +, NUREG-1769, (3:3) Chpt 3 - End, Safety Evaluation Report Related to License Renewal of Peach Bottom Atomic Power Station, Units 2 & 3 +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, 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-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-1828, COMSECY-05-0025 - Renewal of Full-Power Operating License for Arkansas Nuclear One, Unit 2 +, NUREG-1825, Safety Evaluation Report Related to License Renewal of Joseph M. Farley Nuclear Plant, Units 1 & 2 +, 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 + and NUREG-1796, (2:2) Chpt 3 - End, Safety Evaluation Report: Related to the License Renewal of Dresden Nuclear Power Station, Units 2 & 3 and Quad Cities Nuclear Power Station, Units 1 & 2 +
142 +
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Request +
July 11, 2006 +
Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Recirculation Pump +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Standby Liquid Control +, Circulating Water System +, Stator Cooling Water +, Residual Heat Removal Service Water +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod + and Main Steam +
Safe Shutdown +, Boric Acid +, Non-Destructive Examination +, Fire Barrier +, Hydrostatic +, Coatings +, Aging Management +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Moisture barrier +, License Renewal +, Control of Heavy Loads +, EVT-1 +, Through Wall Leak +, Fire Protection Program +, Dissimilar Metal Weld +, Power Uprate + and Water hammer +
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