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NEI Document  and Unfiltered

10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 50.2 +, 10 CFR 2 +, 10 CFR 51 +, 10 CFR 54 +, 10 CFR 2.101 +, 10 CFR 2.108 +, 10 CFR 2.390 +, 10 CFR 50.65 +, 10 CFR 50.90 +, 10 CFR 50.91 +, 10 CFR 50.92 +, 10 CFR 50.109 +, 10 CFR 51.22 +, 10 CFR 51.41, Requirement to Submit Environmental Information +, 10 CFR 50.55a +, 10 CFR 50.54#q +, 10 CFR 50.54#p +, 10 CFR 50.54#a +, 10 CFR 50.91#a5 +, 10 CFR 50.91#a6 +, 10 CFR 50.109#a1 +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +, 10 CFR 51.22#c10 +, 10 CFR 51.22#c +...

COM:JAF-106 +, COM:JAF-11 +, COM:JAF-12 +, COM:JAF-13 +, COM:JAF-14 +  and COM:JAF-2 +

GDC 16 +, GDC 54 +, GDC 56 +, GDC 61 +  and GDC 19, Control room +

NEI 96-07 +, NEI 97-04 +, NEI 96-06 +, NEI 98-03, Submittal of Revision No. 19 to Updated Safety Analysis Report for Monticello +, NEI 06-02, License Amendment Request (LAR) Guidelines +, NEI 01-01, NRC NEI-01-01 Meeting Presentation on 7/31/13 Digital I&C Meeting +  and NEI 99-04, Guideline for Managing NRC Commitment Changes +

NUREG/BR-0058 +, NUREG-0471, Responds to 781113 Request & Encl Generic Task Problem Descriptions(NUREG-0471)& NRC Prog for Resolution of Generic Issues Related to Nuc Pwr Plants(NUREG-0410). W/O Encl +, NUREG/CR-5009, Forwards NUREG/CR-5009, Assessment of Use of Extended Burnup Fuel in Lwrs. Rept Concludes That Environmentally, Burnup Increase Would Have No Significant Impact Over That of Normal Burnup.W/O Encl +, NUREG-0985, Responds to Inquiry Re Concerns of Human Factors Activities at Nrc.Most of Recommendations Noted in Human Factor Society Rept Implemented.State of Human Factors Consideration Both by NRC & Nuclear Industry Advanced Significantly Since TMI +, NUREG-1251, Forwards NUREG-1251, Implications of Accident at Chernobyl for Safety Regulation of Commercial Nuclear Plants in Us. W/O Encl +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0371, Forwards NUREG-0371,NUREG-0471 & NUREG-0600.W/o Encl +, NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

Regulatory Guide 1.177 +, Regulatory Guide 1.25 +, Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, Regulatory Guide 1.187 +, Regulatory Guide 1.186 +  and Regulatory Guide 1.181 +

RIS 2007-06, Implementation +, RIS 2001-22, Attributes of a Proposed No Significant Hazards Consideration Determination +, RIS 2002-22, Use of Epri/Nei Joint Task Force Report, Guideline on Licensing Digital Upgrades: EPRI TR-102348, Revision 1, NEI 01-01: a Revision of EPRI TR-102348 to Reflect Changes to the 10 CFR 50.59 Rule +  and RIS 2000-17, Managing Regulatory Commitments Made by Power Reactor Licensees to the NRC Staff +

TS-JAF-3.9.4 +, TS-JAF-3.6.1 +  and TS-JAF-3.9.4.1 +

TSTF-312 +  and TSTF-400 +

http://pbadupws.nrc.gov/docs/ML1033/ML103360404.pdf  +  and http://adamswebsearch2.nrc.gov/webSearch2/main.jsp?AccessionNumber=ML070650428  +