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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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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Prioritization of Standard Review Plans for Independent Spent Fuel Storage Installations and Dry Cask Storage Systems.

Prioritization of Standard Review Plans for Independent Spent Fuel Storage Installations and Dry Cask Storage Systems NMSS/SFST/TRD The Division of Spent Fuel Storage and Transportation (SFST) initiated a project to update and prioritize the following guidance: NUREG-1536, St...

ACRS Subcommittee briefing on Spent Fuel Transport Risk Assessment (SFTRA).

Hamilton, BrandiFrom: Brown, ChristopherSent: Thursday, January 13, 2011 11:56 AMTo: Cook, JohnCc: Pstrak, David; Weaver, Doug; Ordaz, Vonna; Hackett, Edwin; Santos, CayetanoSubject: ACRS Subcommittee briefing on Spent Fuel Transport Risk Assessment (SFTRA)John,Dr. Ryan has on...

Eastern Associated Coal, LLC, Letter dtd 5/5/2011, Enclosing Corrected Appendix B to Renewal Application.

Eastern ASSOCIATED May 5,2011 Licensing Assistance Team Division of Nuclear Materials Safety U. S. Nuclear Regulatory Commission, Region I 475 Allendale Road King of Prussia, Pa 19406-1415 Dear Sir: Eastern Associated Coal, LU 80.0. Laidley TOWE P.O. Box 123 Charleston, WV 253...

Table 2.B5 for Army Depot Activity.

Date Building MeasurementAlpha DirectBeta DirectUnits Instrument Instrument S/N6/14/1999 2078 27 6 628 cpm Floor monitor 1386696/14/1999 2078 29 11 644 cpm Floor monitor 1386696/14/1999 2078 25 13 654 cpm Floor monitor 1386696/14/1999 2078 30 5 694 cpm Floor monitor 1386696/14...

Reed College Request for Additional Information Regarding License Renewal Application.

March 8, 2010 Mr. Stephen Frantz, Director Reed Reactor Facility Reed College 3203 S.E. Woodstock Boulevard Portland, OR 97202-8199 SUBJECT: REED COLLEGE - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE REED COLLEGE TRIGA REACTOR LICENSE RENEWAL (TAC NO. ME1583) ...

NRC000179 - Regulatory Guide 1.207, Guidelines for Evaluating Fatigue Analyses Incorporating the Life Reduction of Metal Components Due to the Effects of the Light-Water Reactor Environment for New Reactors (Mar. 2007).

The U.S. Nuclear Regulatory Commission (NRC) issues regulatory guides to describe and make available to the public methods that the NRC staffconsiders acceptable for use in implementing specific parts of the agency’s regulations, techniques that the staff uses in evaluating sp...

Close-Out of Fire Probabilistic Risk Assessment Frequently Asked Question 13-0004 on Clarifications Regarding Treatment of Sensitive Electronics.

December 3, 2013 MEMORANDUM TO: APLA Files FROM: Hossein G. Hamzehee, Branch Chief /RA/ PRA Licensing Branch Division of Risk Assessment Office of Nuclear Reactor Regulation SUBJECT: CLOSE-OUT OF FIRE PROBABILISTIC RISK ASSESSMENT FREQUENTLY ASKED QUESTION 13-0...

NuScale ISV Testing Audit Plan.

July 12, 2018 MEMORANDUM TO: Samuel Lee, Chief Licensing Branch 1 Division of Licensing, Siting and Environmental Analysis Office of New Reactors FROM: Prosanta Chowdhury, Project Manager /RA/ Licensing Branch 1 Division of Licensing, Siting and Environmental Analy...

Submits paragraphs which discuss differences noted between TSTF-135 Rev 0 & util submittal dtd 961213 for Section 3.3 LCOs 3.3.1 & 3.3.2.

- - - _ - _ _fQ>mn.nnweahh Frkn GimpanyiWl Opus Pl.n eDowners Grove. !!, M615-5?OiJanuhry 29,199dUn'ited States Nuclear Regulatory CommissionAttenUon: Document Cortrol DeskWashington, DC 20555-0001,Subject:TSTF-135 Revision 0 comparison of Instrumentation Section3.3 for Amendm...

SECY-20-0106: Weekly Information Report - Week Ending October 30, 2020

__________________ INFORMATION REPORT NOVEMBER 17, 2020 SECY-20-0106 FOR: The Commissioners FROM: Catherine Haney Assistant for Operations Office of the Executive Director for Operations SUBJECT: WEEKLY INFORMATION REPORT – WEEK ENDING OCTOBER 30,...

Response to Portion of NRC Request for Additional Information Letter No. 63 Related to ESBWR Design Certification Application - Technical Specifications - RAI Number 16.0-3 S01.

GE-Hitachi Nuclear Energy Americas LLCJames C. KinseyProject Manager, ESBWR LicensingPO Box 780 M/C A-55Wilmington, NC 28402-0780USAT 910 675 5057F 910 362 5057jim.kinsey@ge.comMFN 06-431Supplement 5Docket No. 52-010July 16, 2007U.S. Nuclear Regulatory CommissionDocument Contr...

"Preimplementation Audit Rept for DCRDR for Fermi-2."

f TEnclosure 1-PREIMPLEMENTATION AUDIT REPORT FOR THEDETAILED CONTROL ROOM DESIGN REVIEWFOR_ DETROIT EDIS0N COMPANYFERMI-2_E. E. Schultz, Jr.G. L. JohnsonLawrence Livermore National LaboratoryJune 29, 1987~l|l|||e go g 3,0 0 2 0 kN'!lL--J_( f1|IPREIMPLEMENTATION AUDIT REPORTFO...

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

ITS DISCUSSION OF DIFFERENCESITS Section 3.3C: Instrumentation - EFIC Note: The ITS Section 3.3C package addresses the following NUREG-1430 RSTS: RSTS 3.3.11 EFIC System Instrumentation RSTS 3.3.12 EFIC Manual Initiation RSTS 3.3.13 EFIC Logic RSTS 3.3.14 EFIC Vector Logic I N...

NRC Comments on NEI 17-01 Revision 6 8-16.

NEI 17-01, Comments, Revision 6 Industry Guideline for Implementing the Requirements of 10 CFR Part 54 for Subsequent License Renewal March 2017 NEI 17-01March 20173 NEI 17-01 Nuclear Energy Institute Industry Guideline for Implementing the Require...

Enclosure 2: Draft Safety Analysis Requests for Additional Information for Review of the International Isotopes Fluorine Extraction and Depleted Uranium Facility.

(Public) Draft Safety Analysis Requests for Additional Information for Review of the International Isotopes Fluorine Extraction and Depleted Uranium Facility Table of Contents Table of Contents ..........................................................................

McGuire Initial Exam 2013-301 Draft Sim_IN-Plant JPMs.

Appendix C Job Performance Measure Form ES-C-iWorksheetSIM JPM A2013 Systems - Control Room JPM A (Rev_071213) NUREG 1021, Revision 9Appendix C Page 2 of 10 Form ES-C-iJob Performance Measure WorksheetFacility: McGuire Task No.:Task Title: CA Suction Source Realignment JPM No....

Task Order No. NRC-007 Under Contract No. NRC-HQ-l1-A-42-0028.

SOLICITATIONICONTRACTIORDER FOR COMMERCIAL ITEMS 1. REQUISITION NO. PAGE 1 OF 19OFFEROR TO COMPLETE BLOCKS 12, 17, 23, 24, & 30 8/20/20132. CONTRACT NO. 3. AWARD/EFFECTIVE DATE 4. ORDER NO. 5. SOLICITATION NUMBER 6. SOLCITATION ISSUE DATE/ NRC-HQ-l1-A-42-0028GS1OF0124J 7 /13 N...

"Fracture Toughness of Steam Generator & Reactor Coolant Pump Supports,Indian Point Unit 3," technical evaluation rept.

- _ _ _ _ _ _ _ _ - _ _ - _ _ _ _.._~(INTERIM)TECHNICAL EVALUATION REPORTFRACTURE TOUGHNESS OF STEAM GENERATOR ANDREACTOR COOLANT PUMP SUPPORTSPOWER AUTHORITY OF THE STATE OF NEW YORKINDIAN POINT UNIT 3NRC DOCKET NO. 50-286NRC TAC NO. 08777 FRC PROJECT C5257NRC CONTRACT NO. NR...

2008/12/24 North Anna 3 COL Hearing - FW: Letter from Vanessa E. Quinn Ref: NAPS IFR Open Items

1PMNorthAnna3COLPEmails ResourceFrom: Bruce MusicoSent: Wednesday, December 24, 2008 9:22 AMTo: NorthAnna3COL Resource; Thomas KevernSubject: FW: Letter from Vanessa E. Quinn Ref: NAPS IFR Open ItemsAttachments: 12-23-08 Letter Williams NAPS IFR Open Items.pdf; 12-23-08 Letter...

Turkey Point, Initial Exam 2009-301 Final Simulator/In-Plant JPMs.

Appendix C Facility: Task Title: Job Performance Measure Worksheet Turkey Point Task No: Align Safety Injection For Cold Leg Recirc JPM No: KIA Reference: 006 A4.07 RO 4.4 SRO 4.4 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Form ES-C-1 01200021500 JPMA...

OFFICIAL EXHIBIT - SEI009A-00-BD01 - FSEIS Vol 1, Cover thru App B.

Environmental Impact Statement for the Ross ISR Project in Crook County, Wyoming Supplement to the Generic Environmental Impact Statement for In-Situ Leach Uranium Milling Facilities Final Report Office of Federal and State Materials and Environmental Management Progr...

590272 Request for Additional Information for Andrews University to License No. 21-11654-03.

Garnett B. Cross Radiation Safety Officer Andrews University Department of Physics 4260 Administration Dr. UNITED STATES NUCLEAR REGULATORY COMMISSION REGION Ill 2443 WARRENVILLE RD. SUITE 210 LISLE, IL 60532-4352 July 14, 2016 Berrien Spring, Ml 49104-0380 Dear Mr. Cross: We ...

Incoming Response Letter Dated 11/9/11 for Renewal from Kingsford Manufacturing Company to License No. 24-20121-01.

11/9/2011 Ms. Colleen Carol Casey Materials Licensing Branch United States Nuclear Regulatory Commission Region III 2443 Warrenville road ste 210 Lisle, III 60532·4352 RE: Application Updates for Material License #24-20121-01 Dear Ms. Casey: In response to our phone discussion...

Clarifications On Treatment Of VEWFDS To Support NFPA 805 Risk Analysis.

FAQ Number 13-0001 FAQ Revision 0a FAQ Title Clarifications on Treatment of VEWFDS to Support NFPA 805 Risk Analysis Page 1 of 9 Plant: NextEra Energy ERIN Engineering Duke Energy Date: January 17, 2013 Contact: Vinny Rubano Kiang Zee Joelle DeJoseph Phone: (561) 691-7809 ...

2010/11/12 Turkey Point COL Hearing - FW: Draft RAI 4901 related to SRP Section: 14.03.12 - Physical Security Hardware - Inspections, Tests, Analyses, and Acceptance Criteria for the Turkey Point Units 6 and 7 combined license application.

1PMTurkeyCOLPEm ResourceFrom: Comar, MannySent: Friday, November 12, 2010 2:04 PMTo: Antonio Fernandez; orthen, Richard; TurkeyCOL Resource; William MaherSubject: FW: Draft RAI 4901 related to SRP Section: 14.03.12 - Physical Security Hardware - Inspections, Tests, Analyses, a...