Report a Safety Concern
Search
Home Site Help

NRC Site Search: Search All Sites

Filter by Document Type

Sort Documents by

Three Mile Island, Unit 1, License Renewal Application, Section 3.0 Aging Management Review Results through Table 2.5-1, Electrical Commodity Groups.

Section 3 – Aging Management Review Results _________________________________________________________________________________________________ Three Mile Island Nuclear Station Unit 1 Page 3.0-1 License Renewal Application 3.0 AGING MANAGEMENT REVIEW RESULTS This section provi...

Forwards response to NRC 871031 request for review of tabulation of status of implementation of generic regulatory required improvements for facility.

REGULA Y INFORMATION DISTRIBUTI YBTEM (RIDB)ACCESSION NBR: 87111'F0136 DOC. DATE: 87/11/16 NOTARIZED: NO DOCKET IFACIL: 50-220 Nine Mile Point Nuclear Stations Unit ii Niagara Powe 05000220AUTH. NAME AUTHOR AFFILIATIONMANGANiC. V. Niagara Mohawk Power Corp.RECIP. NAME RECIPIEN...

Advises that NRC 810826 draft evaluation of SEP Topic XV-9, "Startup of Inactive Loop,Flow Controller Malfunction," reviewed.Assessment accurately represents as-built condition at plant.

air~ »r ~ ~ 0(r/ e ~ «», a,'t,e»e» >i4NUI a»»4 eJJr'llROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649»0&N c,. IIAIERIICr PRESIDKNTreeepmONeacre COOe . ia 5 "6-2700October 16, 1981Director of Nuclear Reactor RegulationAttention: Mr . Dennis M. Cru...

"PWR Safety & Relief Valve Adequacy Rept for AL Power Co, Joesph M Farley Unit 1 & Unit 2."

.,_ __e,. . , -ATTACHMENT I*,i.PWR SAFETY AND RELIEF VALVEADEQUACY REPORTFORALABAMA POWER C0dPANYJOSEPH H. FARLEY UNIT 1 AND UNIT 2JUNE 25, 1982i'Prepared By '; R'. M. Gray n/Approved By: iR. E.IKelly', ManderPump and Valve Engineeringi!;Westinghouse Electric CorporationNuclea...

University of Utah, Request for Additional Information, Renewal Application and Power Uprate Review (TAC ME1599).

February 22, 2010 Dr. Tatjana Jevremovic Director, Utah Nuclear Engineering Program Joseph Merrill Engineering Building 50 Central Campus Drive, Room 2298 University of Utah Salt Lake City, UT 84112 SUBJECT: UNIVERSITY OF UTAH - REQUEST FOR ADDITIONAL INFORMATION REGARDI...

"Control of Heavy Loads at Nuclear Power Plants,Perry Nuclear Power Plant Units 1 & 2,Cleveland Electric Illuminating Co," draft.

,~o s.* * .,-.. ..,,..-< ,v,. .,..\.' -'C0t; TROL OF HEAVY L0A05 AT NUCLEM POWER PLANTSPERRY NUCLEAR POWER PLANT UNITS 1 AND 2-THE CLEVELAND ELECTRIC ILLUMINATING COMPANY00cket No. 50-440 & 50-441;AutnorJ.'C. Rawers.Principal Tecnnical InvestigatorT. Hi Stickley',.EG&G Idano, ...

Responds to 921228 request to evaluate current classification for loss of annunciators & to revise emergency classification & EALs.Concludes that current guidance for treating loss-of-annunciator events,adequate.

/f, N UNhTED STATESNUCLEAR REGULATORY COMMISSION/g$|wassiwaTow. o. c.aoses) ,,,1*....February 4, 1993!1MEMORANC' M FOR: James H. Sniezek J

SRP, Appendix A-3, April 2001

April 2001 A.3-1 NUREG-1800A.3 GENERIC SAFETY ISSUES RELATED TO AGING(BRANCH TECHNICAL POSITION RLSB-2)A.3.1 BackgroundUnresolved Safety Issues (USIs) and Generic Safety Issues (GSIs) are identified and tracked inthe NRC’s formal resolution process set forth in NUREG-0933, “A...

Lehigh Valley Cardiology Associates, Renewal - Performance Evaluation Checklist dtd 11/29/2004.

APPENDIX C Performance Indicator Escalated enforcement, or 01 or OIG investigation occurred or ongoing Lost control of licensed material presumed in public domain that is reportable or resulted in a violation Unauthorized disposal or release of material that is reportable or r...

State-of-the-Art Reactor Consequence Analyses (SOARCA) Project

UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 May 15, 2012 The Honorable Gregory B. Jaczko Chairman U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 SUBJECT: STATE-OF-THE-ART REACTOR CONSEQUEN...

EPRI/NRC-RES Fire Human Reliability Analysis Guidelines (PSAM PowerPoint Presentation).

EPRI/NRC-RES Fire Human Reliability Analysis Guidelines Susan Coopera*, Kendra Hilla1, Stacey Hendricksonb, John Foresterb2, Jeff Juliusc, Jan Grobbelaarc, Kaydee Kohlheppc, Bill Hannamand, Erin Collinsd, Bijan Najafid, and Stuart R. Lewise aU.S. Nuclear Regulatory Commis...

G20070143 - Supplementary Response to Recommendations in OIG-06-A-24, "Evaluation of the NRC's Use of Probabilistic Risk Assessment in Regulating the Commercial Nuclear Power Industry".

April 25, 2007MEMORANDUM TO: Stephen D. DingbaumAssistant Inspector General for AuditsOffice of the Inspector GeneralFROM: Martin J. Virgilio /RA/Deputy Executive Director for Materials, Waste, Research, State, Tribal, and Compliance ProgramsOffice of the Executive Directo...

0501 - P102 - Bayesian Inference in Risk Assessment - 06 - Secondary References.

Idaho National Engineering and Environmental LaboratorySecondary References Secondary References• • “Evaluation of Loss of Offsite Power Events at Nuclear “Evaluation of Loss of Offsite Power Events at Nuclear Power Plants: 1980 Power Plants: 1980- -1996,” NUREG/CR 1996,” NU...

WNP2-INIT EXAM-10/2000-DRAFT OUTLINES

Facility: WNP-2 Knowledge and Ability Record Form Exam date: October 23, 2000ref: NUREG - 1021 rev 8BWR RO EXAM OUTLINE ES-401-2page 1bold face indicates K/As common to both RO and SRO ...

FSME-07-110, Publication of NRC Guidance About Commercial Radiopharmacy Licenses.

December 12, 2007 ALL AGREEMENT AND NON-AGREEMENT STATES STATE LIAISON OFFICERS PUBLICATION OF NRC GUIDANCE ABOUT COMMERCIAL RADIOPHARMACY LICENSES (FSME-07-110) Purpose: To inform the States that NUREG-1...

More Information Item #47.

1 NRC Risk-Informed Activities September 2014Public Website – Annual Update RES-DRA Treatment of PRA Uncertainties To support risk-informed regulatory activities, how uncertainties associated with PRA should be factored into the risk-informed decisionmaking process needs t...

Fire Risk Research Triangle Poster Reference and CD Contents.

FIRE RISK RESEARCH TRIANGLE POSTER REFERENCE AND CD CONTENTS• Distributed at 2006 Regulatory Information Conference (RIC) poster session• Fire Risk Research Triangle poster available through public NRC website under RIC• CD contents (available through NRC public website unless...

FSER - VCSNS Chapter 18 Clean Master, Human Factors Engineering.

18-1 18.0 HUMAN FACTORS ENGINEERING 18.1 Overview (No Corresponding Section in Regulatory Guide (RG) 1.206) Section 18.1 of the V.C. Summer Nuclear Station (VCSNS) combined license (COL) Final Safety Analysis Report (FSAR), Revision 5, incorporates by reference, with no dep...

EPFAQ 2019-03 Clarification of Clock Initiation for Determination of a Significant Radiological Release in EPFAQ 2013-004

Emergency Preparedness Program Frequently Asked Question (EPFAQ) 1 EPFAQ Number: 2019-03 Originator: Dean Burnett Organization: Entergy Relevant Guidance: This question requests clarity on the clock initiation for determination of a Significant Radiological Release...

2016/01/22 APR1400 DCD RAI - APR1400 Design Certification Application RAI 373-8480 (18 - Human Factors Engineering)

1KHNPDCDRAIsPEm ResourceFrom: Ward, WilliamSent: Friday, January 22, 2016 12:57 PMTo: apr1400rai@khnp.co.kr; KHNPDCDRAIsPEm Resource; daegeun.ahn@gmail.com; Andy Jiyong Oh; Erin Wisler (erin.wisler@aecom.com)Cc: Lee, Samuel; Ciocco, Jeff; Kent, Lauren; Junge, Michael; Ward, Wi...

REG CON, October 31 through November 1, 2017, Presentation: Best Practice Guidelines for the Use of CFD in Dry Cask Applications, J. Solis, NRC.

Best Practice Guidelines for the Use of CFD in Dry Cask ApplicationsJorge SolísUnited State Nuclear Regulatory CommissionRockville, MarylandOctober 31st, 2017Introduction• NRC’s technical review of dry cask designs is performed in accordance with 10 CFR Part 72 and the Standa...

Nine Mile Point, Units 1 and 2 - License Renewal Application, Reformatted Sections, 3.1.2., 3.2.2., 3.3.2., 3.4.2., 3.5.2., 3.6.2. (TAC Nos. MC3272 and MC3273).

- .. .Constellation Energy:A Nine Mile Point Nuclear StationP.O. Box 63Lycoming, NY 13093August 19,2005NMP1L 1976U.S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555-0001SUBJECT: Nine Mile Point Units 1 and 2Docket Nos. 50-220 and 50-410Facility Op...

SE Chpt 18 - VCSNS SE Chapter 18 CLEAN Master "Human Factors Engineering."

V.C. Summer Nuclear Station Units 2 and 3 18-1 18.0 HUMAN FACTORS ENGINEERING 18.1 Overview (No Corresponding Section in Regulatory Guide (RG) 1.206) Section 18.1 of the V.C. Summer Nuclear Station (VCSNS) combined license (COL) Final Safety Analysis Report (FSAR), Re...

OIG-15-A-15-Status of Recommendations: Audit of NRC's Regulatory Analysis Process dated May 16, 2019.

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 OFFICE OF THE INSPECTOR GENERAL May 16, 2019 MEMORANDUM TO: Margaret M. Doane Executive Director for Operations FROM: Dr. Brett M. Baker /RA/ Assistant Inspector General for Audits ...

Availability of Final Rule: Continued Storage of Spent Nuclear Fuel.

September 22, 2014 SUBJECT: PUBLICATION OF FINAL RULE – CONTINUED STORAGE OF SPENT NUCLEAR FUEL (RIN 3150-AJ20; NRC-2012-0246) Greetings, This is to inform you that the U.S. Nuclear Regulatory Commission (NRC) has published the final rule, “Continued Storage of Spent ...