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ML24072A005 +
10 CFR 50.67 +, 10 CFR 21 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 30 +, 10 CFR 20 Appendix B +, 10 CFR 51 +, 10 CFR 20.1301 +, 10 CFR 50.60 +, 10 CFR 50.61 +, 10 CFR 50.90 +, 10 CFR 50 Appendix H +, 10 CFR 50 Appendix I +, 10 CFR 51.21 +, 10 CFR 100.11 +, 10 CFR 50.55a +, 10 CFR 50.54#p +, 10 CFR 50.36#c5 +, 10 CFR 50.36#c4 +, 10 CFR 73.55#c7 +, 10 CFR 20.1301#e +, 10 CFR 20.1302#b2ii +, 10 CFR 20.1302#b2 + and 10 CFR 50.71#e +
ML050120209 +, ML110660285 +, ML070550060 +, ML100351425 +, ML070100635 +, ML070740002 +, ML16077A093 +, ML16159A057 +, RIS 2014-11, Information on Licensing Applications for Fracture Toughness Requirements for Ferritic Reactor Coolant Pressure Boundary Components +, CNL-17-144, Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) +, ML040620297 +, ML18204A010 +, ML993160096 +, ML18347B330 +, ML112720411 +, ML003759282 +, ML993160101 +, ML18338A516 +, CNL-21-010, Correction of Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology (WBN-TS-19-04) (EPID +, ML21034A169 +, ML21148A100 +, NUREG-1431 Volume 1, Rev. 5, Standard Technical Specifications Westinghouse Plants: Specifications +, ML20209H927 +, WBL-21-056, Revised Pressure and Temperature Limits Report (PTLR) +, ML22153A139 +, WBL-20-004, Analysis of Capsule U from Watts Bar Unit 2 Reactor Vessel Radiation Surveillance Program +, CNL-23-002, Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN-TS-21-02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Sche +, WBL-23-018, Revised Pressure and Temperature Limits Report (PTLR) +, ML23150A247 +, ML16343A235 +...
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ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +, ML24072A005 +...
April 15, 2024 +
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00:46:50, 25 November 2024 +
NUREG-1431 +, NUREG-0847, Suppl. 22, Safety Evaluation Report, Related to the Operation of Watts Bar Nuclear Plant, Unit 2 +, NUREG-1672 +, NUREG/CR-2907, Responds to 851105 Request for Info Re Radwaste & Containment Spray Sys.Nrc Methodology for Estimating Radwaste Generation Delineated in Encl NUREG-0017.USA Experience Summarized in Encl NUREG/CR-2907.W/o Encls +, NUREG-0713, Vol.43, Occupation Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2021: Fifty-Fourth Annual Report + and NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +
1 +
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Approval +
April 15, 2024 +
Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report +
Ultimate heat sink +, Offsite Dose Calculation Manual +, Anticipated operational occurrence +, Hydrostatic +, Cyber Security +, Incorporated by reference +, Loss of Offsite Power +, Safeguards Contingency Plan +, Tritium Producing Burnable Absorber Rods +, Exemption Request +, Fire Protection Program +, Control Room Habitability + and Pressure Temperature Limits Report +
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