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ML17130A330 +
10 CFR 50 Appendix A +, 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 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 54.4#a2 +, 10 CFR 54.37#b +, 10 CFR 54.21#d +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1ii +, 10 CFR 54.21#c1iii + and 10 CFR 50.71#e +
NRC Generic Letter 81-11, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking (NUREG-0619) +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping + 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>.
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April 6, 2017 +
ML20036A070 + and ML20058K266 +
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>.
13:27:34, 9 January 2025 +
NUREG/CR-6260 +, NUREG/CR-0609 +, NUREG-1769, (3:3) Chpt 3 - End, Safety Evaluation Report Related to License Renewal of Peach Bottom Atomic Power Station, Units 2 & 3 + and 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 +
44 +
Supplement +
NEDC-33566P + and NEDC-32983P +
April 6, 2017 +
Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Primary Containment Isolation System +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Pressure Vessel +, Core Spray +, Standby Gas Treatment System +, Fuel Pool Cooling and Cleanup +, Standby Liquid Control +, Emergency Core Cooling System +, Safety Relief Valve +, Control Rod + and Main Steam +
6 to Updated Final Safety Analysis Report, Appendix Q, License Renewal Aging Management UFSAR Supplement +
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