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ML16120A326 +
10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50.59 +, 10 CFR 72 +, 10 CFR 54 +, 10 CFR 2.109 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.65 +, 10 CFR 50 Appendix E +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 50 Appendix I +, 10 CFR 54.21 +, 10 CFR 50.61a +, 10 CFR 50.55a +, 10 CFR 54.4#b +, 10 CFR 50.49#f +, 10 CFR 50.49#e5 +, 10 CFR 50.54#q +, 10 CFR 54.37#b +, 10 CFR 50.61#b4 +, 10 CFR 54.21#d +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1ii +, 10 CFR 54.21#c1iii +, 10 CFR 54.21#c +...
NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 85-11, Completion of Phase II of "Control of Heavy Loads at Nuclear Power Plants" NUREG-0612 + and NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +
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ML16120A326 +, ML16120A326 +, ML16120A326 +, ML16120A326 +, ML16120A326 +, ML16120A326 +, ML16120A326 +, ML16120A326 +, ML16120A326 +, ML16120A326 +, ML16120A326 +, ML16120A326 +, ML16120A326 +, ML16120A326 +, ML16120A326 +, ML16120A326 +, ML16120A326 +, ML16120A326 + and ML16120A326 +
April 18, 2016 +
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05:37:21, 10 January 2025 +
NEI 96-03 +, NEI 97-06, Steam Generator Conditioning Monitoring Report + and 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 . +
NUMARC 87-00 + and NUMARC 93-01 +
NUREG-1432 +, NUREG/CR-5704 +, NUREG/CR-6260 +, NUREG/CR-6583 +, NUREG/CR-5999, Forwards Updated Fatigue Design Curves for Austenitic Stainless Steels in LWR Environments.Design Curves Being Provided in Advance of Future Update of NUREG/CR-5999 to Facilitate Efforts on Resolution of GSI-190 +, 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-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, 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-0820, Safety Evaluation Supporting Amend 125 to License DPR-20 +, NUREG-0410, Speech Entitled Shutdown Decay Heat Removal, for Presentation at 890418-20 NRC Regulatory Info Conference in Washington,Dc +, NUREG-0554, Responds to to Chairman Jackson Re Resolution of Berkeley Township Environ Commission. Forwards Reply to L Worrall Which Contains Directors Decision,Per 10CFR2.206 +, NUREG-1424, Forwards SER of Util 900122 Application Re full-term OL for Plant.Conversion of Provisional OLs Subsumed in SEP Program. Issues Releval to Provisional OL Conversions Not Covered in SEP Program,Covered in Ser.W/O Encl +, NUREG-1871, Safety Evaluation Report Related to the License Renewal of Palisades Nuclear Plant +, 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 +
89 +
Request +
April 18, 2016 +
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Circulating Water System +, Emergency Core Cooling System +, Decay Heat Removal +, Safety Relief Valve +, Control rod blade +, Main Condenser +, Control Rod + and Containment Spray +
Final Safety Analysis Report Update, Revision 32, Chapter 1 - Introduction and General Description on Plant - Sections +
Safe Shutdown +, Boric Acid +, Shutdown Margin +, High Radiation Area +, Ultimate heat sink +, Non-Destructive Examination +, Fire Barrier +, Weld Overlay +, Probabilistic Risk Assessment +, Coatings +, Operating Basis Earthquake +, Nondestructive Examination +, VT-2 +, Aging Management +, Flow Accelerated Corrosion +, Feedwater Heater +, Microbiologically influenced corrosion +, Stress corrosion cracking +, Eddy Current Testing +, Moisture barrier +, License Renewal +, Earthquake +, Control of Heavy Loads +, Fuel cladding +, Biofouling +, Fire Protection Program +, Backfit +, Power change +, Siren +, Control Room Habitability +...
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