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The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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Forwards Insp Rept 50-285/86-11 on 860414-18.No violations or deviations noted.Schedule for correcting identified deficiency re emergency preparedness program requested within 30 days.

y~q,m,*-*;y g gg-1 1In Reply Refer ToiDocket: ,50-285/86-11Omah'a Public Power District; ATTN:R. L..Andrews, Division Manager-' Nuclear Production.11623 Harney StreetOmaha,-Nebraska 68102Gentlemen:'-This refers to the inspection conducted by Messrs. J. B. Baird and C. A.'Hackn...

Engineering Calculation No. ENG-003, Revision 0, "Calculation of EF1 Building Surface DCGLs."

T-738 P-002/004 F-134OCT-07-2008 07:23PM FROM---3 .D2f~ -3(5W8A RT L ETTENGINEERING CALCULATIONCalculation Number: ENG-003Revision Number: Q, 0.1Calculation Title9Calculation of EFI1 Buildirng Surface DCGLsItalculation of EF I BulldinE Surface DPreparer:Reviewer:A,0,ovI: ject ...

Korea Hydro and Nuclear Power Co., Ltd - Response to RAI 53-7982.

18-2 - 1 / 3 KEPCO/KHNP RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION APR1400 Design Certification Korea Electric Power Corporation / Korea Hydro & Nuclear Power Co., LTD Docket No. 52-046 RAI No.: 53-7982 SRP Section: 18 – Human Factors Engineering Application Section: ...

G20130508 - Stephen D. Dingbaum Memo re Status of Recommendations: The Nuclear Regulatory Commission's Oversight of Industrial Radiography (OIG-12-A-15).

January 28, 2014 MEMORANDUM TO: Stephen D. Dingbaum Assistant Inspector General for Audits Office of the Inspector General FROM: Brian E. Holian, Acting Director /RA by Marian Zobler for/ Office of Federal and State Materials and Environmental Management P...

Enclosure 3: Handouts - Licensing and Oversight Program Improvements.

Licensing and Oversight Program ImprovementsChristopher StaabSpent Fuel Storage and Transportation, NMSSU.S. Nuclear Regulatory CommissionMarch 28, 20111Today’s Outline- NUREG-1745 Update (Chris Staab, NRC)- Inspection Guidance Enhancement (Tom Matula, NRC)- Suggestions for 7...

Requests markup by 860531 of encl plant-specific list, including omitted significant actions & date that all aspects of each identified requirement completed/ implemented,to aid NRC in long-term program development.

'... .April 30,,1986,Docket No. 50-333 DISTRIBUTION6 Docket File 1;OELDMr. John C. Brons NRC PDRACRS(10)Senior Vice President - Local PDR EJordanNuclear Generation Gray File BGrimesPower Authority of tf.e State RBernero JPartlowof New York SNorris HSmith123 Main Street HAbelso...

Connecticut Veterinary Center, RAI, Request for Additional Information Concerning Application for New License, Control No. 140471.

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I475 ALLENDALE ROADKING OF PRUSSIA, PENNSYLVANIA 19406-1415 May 29, 2007Docket No. 030-37465 License No. 06-31245-01Control No. 140471Anne Masloski, DVMMedical DirectorConnecticut Veterinary Center470 Oakwood AvenueWest H...

Interim Staff Guidance Associated with License Applications

This page includes links to files in non-HTML format. See Plugins, Viewers, and Other Tools for more information.ISG NumberTitleStatus/CommentDANU-ISG-2022-01Review of Risk-Informed, Technology-Inclusive Advanced Reactor Applications—RoadmapOPEN   Draft&nbs...

Rancho Seco Nuclear Generating Station License Termination Plan, Chapter 6, Compliance with the Radiological Criteria for License Termination, Appendix 6-A, RESRAD Parameters for Soil Dose Modeling Probabilistic Analysis.

Rancho Seco License Termination Plan Revision 0 Chapter 6, Compliance With the Radiological Criteria for License Termination April 2006 Appendix 6-A, RESRAD Parameters for Soil Dose Modeling Probabilistic Analysis Page 6-63 Parameter Class1 Priority2Units Parameter Value Bas...

Responds to Generic Ltr 89-21 re implementation status of USI requirements at facilities.PRA to address USI A-17, "Sys Interactions in Nuclear Power Plants" will be completed in Feb 1993.

!?-4'.-''I;INos1hern States Power Comparty ||414 Nicollet Mall )Minneapolis, Minnesota 55401 1927)gTelephone (612) 330-55001December 1. 1989Response tofGeneric Letter.89 21rwer ,(IDEh.j,s...,,, , , ,- . ;W,,. M ation ,-' ,,**USNuclearRegulatorycomad.,N.y'onWashington DC 205f5,...

C--fX -,aUNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555-0001November 23, 1999NRC REGULATORY ISSUE SUMMARY 99-04SOURCES OF INFORMATION PREVIOUSLY PUBLISHEDIN THE AEOD ANNUAL REPORTADDRESSEESAll NRC licensees.INTENTTo inform ...

Shine Project Update Meeting Slides.

Introductions  Dr. Greg Piefer, SHINE Chief Executive Officer  Dr. Vann Bynum, SHINE Chief Operating Officer  Eric Van Abel, Nuclear Engineer  Jim Freels, SHINE Licensing  Open to Public  Licensing Discussion ▪ License Application Approach ▪ License Application Struc...

NRC Staff Evaluation of FMRI Response to RAIs on DCGLs.

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 23, 2017 Mr. Robert Compernolle President, FMRI FMRI, Inc. Number 10 Tantalum Place Muskogee, OK 74403 SUBJECT: NRC STAFF EVALUATION OF FMRI REVISED DERIVED CONCENTRATION GUIDELINE LEVELS (DC...

Draft Regulatory Guide DG-3028 (Proposed RG 3.66 Rev. 1) Standard Format and Content of Financial Assurance Mechanisms Required for Decommissioning Under 10 CFR Parts 30, 40, 70, and 72.

This regulatory guide is being issued in draft form to involve the public in the early stages of the development of a regulatory position in this area. It has not received final staff review or approval and does not represent an official NRC final staff position. Public com...

NFPA 805 Transition Pilot Plant FAQ 08-0053, Kerite FR Cable Failure Thresholds.

FAQ Number 08-0053 FAQ Revision 0 FAQ Title Kerite FR Cable Failure Thresholds Page 1 of 7 Plant: Cooper Nuclear Station Date: September 19, 2008 Contact: Thomas Shudak Phone: (402) 825-2984 Email: TGShuda@nppd.com Distribution: (NEI Internal Use) 805 TF FPWG RAT...

OEDO-17-00346 - Consequential Steam Generator Tube Rupture.

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 27, 2017 Dr. Dennis Bley, Chairman Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 SUBJECT: CONSEQUENTIAL STEAM GENERATOR TUBE RUPTURE Dea...

2009/03/2/-OFFICIAL EXHIBIT - MANDATORY HEARING - NRC000075-MA-BD01 - Curriculum Vitae for James V. Ramsdell, Jr.

RESUME JAMES V. RAMSDELL, JR. Senior Technical Researcher Radiological Sciences & Engineering Group Battelle, Pacific Northwest Laboratories EDUCATION B.S. General Sciences, Oregon State 1961 ...

Nuclear Energy Institute - PWR & BWR Knowledge and Abilities Master Catalogs.

TIMOTHY RITI Senior Projed Manager, Regulatory Affairs 1201 F Street, NW, Suite 1100 · Washington, DC 20004 P: 202.739.8137 txr@nei.org nei.org January 29, 2019 Ms. Aida Rivera-Varona Chief, Operator Licensing and Training Branch Division of Inspection and Regional Support Off...

Comment (1) of Carol L. Campbell on Behalf of U.S. Environmental Protection Agency on Final Supplemental Environmental Impact Statement for the Lost Creek ISR Project.

,\AAOST4) UNITED STATES ENVIRONMENTAL PROTECTION AGENCY "// - //'/ -iQ T REGION 8- 1595 Wynkoop StreetDENVER, CO 80202-11294 PRO1%e Phone 800-227-8917http://www.epa.gov/region08JUL22lJ L2,5 2011--Ref: EPR-NDrew Persinko, Deputy Director --U.S. Nuclear Regulatory CommissionEnvi...

Deviation from NRC-Approved Fire PRA Methods, NRC FPRA FAQ Public Meeting March 21, 2013.

Deviation from NRC-Approved Fire PRA Methods PRA Methods NRC FPRA FAQ Public MeetingMarch 21, 2013Suggested Definition Suggested Definition• Deviation from NRC-Approved Fire PRA Deviation from NRC Approved Fire PRA Methods – An approach, method, or data, which is unique to pp ...

Part IV - Arkansas Nuclear One - Unit 1, Improved Technical Specifications Submittal, Volume 2 of 2.

ITS DISCUSSION OF DIFFERENCESITS Section 3.8: Electrical Power Systems NUREG LCO 3.8.1 .c, NUREG 3.8.1 Condition F, & NUREG SR 3.8.1.11, [3..-01 SR 3.8.1.18, SR 3.8.1.19 and NUREG 3.8.2 LCO Bases - The automatic load sequencing design for this unit is provided by individual ti...