Report a Safety Concern
Search

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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Home Site Help

NRC Site Search: Search All Sites

Filter by Document Type

Sort Documents by

US-APWR Design Certification - SRP Section: 09-03.03 - Equipment and Floor Drainage System Application Section: 9.3.3 - Questions for Balance of Plant Branch 2 (ESBWR/ABWR) (SBPB).

REQUEST FOR ADDITIONAL INFORMATION 299-2036 REVISION 1 14/1/2009 US-APWR Design Certification Mitsubishi Heavy Industries Docket No. 52-021 SRP Section: 09.03.03 - Equipment and Floor Drainage System Application Section: 9.3.3 QUESTIONS for Balance of Plant Branch 2 (E...

IR 05000390-74-007 and 05000391-74-007; 12/4-5/1974 and 12/10-13/1974; Tennessee Valley Authority; Watts Bar Units 1 and 2.

. UNITED STATES"-ATOMIC ENERGY COMMISSIONDIh.CTOF{ATC. OF REGIJLAtTORY OPERATIONSREGION II - SUITE 81823y) PEAEýHT REE STREETF NORTHWEST T 14O41 USo.4C1-filATLANTA. GEORGIA 30303In Reply Refer To: JAN 6 1975RO: II: VLB50-390/74-750-391/74-7Tennessee Valley AuthorityATTN: Mr. J...

Point Beach, Units 1 and 2 - Generic Letters 81-07 and 85-11, Clarification of Licensing Basis for Control of Heavy Loads.

aSuNMC oPoint Beach Nuclear PlantCommitted to NuclearExceI Operated by Nuclear Management Company, LLCApril 12, 2005NRC 2005-004510 CFR 50.71 (e)U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555Point Beach Nuclear Plant, Units 1 and 2Dockets 50-...

Draft - A Safety Assessment of NAC's Multipurpose Dry Storage Systems in the Face of Militant Acts of Destructiveness (MADness).

DRAFTA SAFETY ASSESSMENT OF NAC'S MULTIPURPOSE DRY STORAGESYSTEMS IN THE FACE OF MILITANT ACTS OF DESTRUCTIVENESS(MADness) lCharles W. Pennington -,Senior Vice President, Marketing & Business DevelopmentNAC InternationalPJi,INTRODUCTIONThe events of September 11 have reverbera...

AP1000 COL Response to Requests for Additional Information (TR 106).

( )W estinghouse e,~o o.co n Westngho -s'eWestinghouse Electric CompanyNuclear Power PlantsP.O. Box 355Pittsburgh, Pennsylvania 15230-0355USAU.S. Nuclear Regulatory Commission Direct tel: 412-374-6306ATTENTION: Document Control Desk Direct fax: 412-374-5005Washington, D.C. 205...

Browns Ferry Units 1, 2 & 3, Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Response to Round 25 - Request for Additional Information - SCVB-82 Through SCVB-86 and Replacement Documentation.

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402-2801July 29, 200910 CFR 50.90U. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, D.C. 20555-0001Browns Ferry Nuclear Plant, Units 1, 2, and 3Facility Operating License Nos. DPR-3...

Waterford 3 01/2002 Final Operating Exam Outlines.

Appendix D Scenario Outline Form ES-D-1Facility: Waterford III Scenario No.: 1 Op-Test No.: 1Examiners: ____________________________ Operators: __________________________ ____________________________ __________________________ __...

WRAIR Attachment 1, Resrad Build Output Report for Residual Contamination in Room GR.

NWTFinal Report Rev. 1Walter Reed Army Institute Of Research ...

Edwin I. Hatch Nuclear Plant Unit Nos. 1 and 2, Issuance of amendments Nos. 110 and 48, revising TS to add proposed Radiological Effluent Technical Specifications Appendix A to license and to delete radiological TSs from Appendix B to license.

June 28, 1985Dockets Nos. 50-321 and 50-366 Mr. J. T. Beckham, Jr. Vice President - Nuclear Generation Georgia Power Company P. 0. Box 4545 Atlanta, Georgia 30302D ISkRUTIjFjON NRC PDR L PDR ORB#4 Rdg HThompson OELD EJordan BGrimesJPartlow ACRS-10 RIngram GRivenbark Gray File...

Crystal River, Unit 3, License Amendment 81, Amendment Permits Triaxial Peak Accelograph on Top of Reactor Vessel Head to be Inoperable During Modes 5 & 6.

September 18, 1985Docket No. 50-302 Mr. Walter S. Wilgus Vice President, Nuclear Operations Florida Power Corporation ATTN: Manager, Nuclear Licensing & Fuel Management Post Office Box 14042; M.A.C. H-2 St. Petersburg, Florida 33733 Dear Mr. Wilgus:DIST zz_~et Fil_ N NRC PDR L...

Responds to NRC ltr re violations noted in insp rept 50-286/93-13 on 930601-0719.Corrective actions:Surveillance Test 3PT-3Y1 reviewed & revised by 931031.

Indian Point 3 Nuclear Power Plant P0 Box 215 Buchann New'. York 10511 991 736.300iO NewYork Power 4 AuthoritySeptember 22, 1993 IPN-93-110 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop PI-137 Washington, D.C. 20555 Subject: Indian Point 3 Nuclear Po...

Surry Power, Units 1 & 2 - Technical Specifications Bases Changes Revision of References for Offsite Dose Limits.

VIRGINIA ELECTRIC AND POWER COMPANYRICHMOND, VIRGINIA 23261May 31, 2005U. S. Nuclear Regulatory CommissionAttention: Document Control DeskWashington, D.C. 20555Serial No. 05-319SPS-LIC/CGL RO'Docket Nos. 50-28050-281License Nos. DPR-32DPR-37VIRGINIA ELECTRIC AND POWER COMPANYS...

Request for Additional Information for the Review of the Columbia Generating Station, License Renewal Application.

June 21, 2010 Mr. W.S. Oxenford, Vice President Nuclear Generation and Chief Nuclear Officer Columbia Generating Station Energy Northwest MD PE08 P.O. Box 968 Richland, WA 99352 SUBJECT: REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE COLUMBIA GENERATING STATION...

RO:on 711104,fire at primary auxiliary bldg damaged essential auxiliary electrical components.Cause under investigation.Detailed event analysis encl.

WilliamE.Cld.& L rt ' Vice President W NoV, .egulato ..- ( File Cy. , , i Consolidated Edison Company of New York, Inc. ' ect,0 5 / 4 Irving Place, New York, N Y 10003 Telephone (212) 460-5181 November 14, 1971 Re: Indian Point Station Unit No. 2 Docket No. 50-247 Dr. Peter A...

Request for Additional Information 483-3885, Revision 1, US-APWR DC, SRP Section: 09.04.03 - Auxiliary and Radwaste Area Ventilation System.

REQUEST FOR ADDITIONAL INFORMATION 483-3885 REVISION 1 111/9/2009 US-APWR Design Certification Mitsubishi Heavy Industries Docket No. 52-021 SRP Section: 09.04.03 - Auxiliary and Radwaste Area Ventilation System Application Section: 9.4.3 QUESTIONS for Containment and ...

Proposed TS 3/4.3.2.1,Table 3.3-3,safety features actuation sys instrumentation,reflecting design & actuation logic of plant sequencers & essential bus undervoltage relays.

LAR 93-0003Page 12,.3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RECITIRENDrfs3/4.0 APPLICASILITTLIMIT"lC CONDITION FOR OPERATION3.0.1 Limiting Conditions for Operation and ACTION requiraseets shall beapplicable during the OPERATIONAL MODES or. other conditions speci...

Framatome: 2018 - Annual Reporting of Changes and Errors in Emergency Core Cooling Systems (ECCS) Evaluation Models.

framatome May 1, 2019 NRC:19:008 U.S. Nuclear Regulatory Commission Document Control Desk 11555 Rockville Pike Rockville, MD 20852 fflD) 011...'l c;qq 02 ot/ l 2018 - Annual Reporting of Changes and Errors in Emergency Core Cooling Systems (ECCS) Evaluation Models Ref. 1: Lett...

LER 87-067-00:on 870926,Tech Spec leakage limit exceeded due to excessive leakage rate through main steam line B isolation valves.Caused by separation of stem & actuator on inboard MSIV due to improperly installation.Seat relapped.

RC peeln 3s4U.S. NUCLitJI f.EGULATO2Y COMMISSIONAPPROVED OM8 NO. 3161Nno4LICENSEE EVENT REPORT (LER)Ents senienF ACILITY NAM 8 IllDOC 4tT NUM64R (2) P AGE tJaporrv hel one Pnuer P1nnt. Unit 10 | 5 | 0 | 0 | 01414 10 1 |0d 014' " ' ' ' ' 'I'mproper Maintenance Results in The B ...

Insp Rept 50-309/89-13 on 890622-0731.No violations noted. Major areas inspected:operational safety verification,maint, surveillance,physical security & radiation protection.

, , . . _ - _ . -)i.T-y:. . s. n......,,p..; ?,5-,9U.S. NUCLEAR. REGULATORY CCMMISSION,,.. REGION I. ,; .: ve4w 5,.m'5.: ; Surveillance (IP6172Qkt , ' ,' ' ' 'The inspector observed parts of testi to assess' performance in accordance-with approved performane n nd LCOs, test re...

Monthly operating rept for Aug 1986.W/860911 ltr.

_..AVERAGE DAILY UNIT POWER LEVELDocket No. 50-272Unit Name Salem # 1.Date September 10,19.86Completed by Pell White Telephone609-935-6J00Extension 4451MonthAugust 1986Day Average Daily Power Level Day Average Daily Power Level(MWe-NET) (MWe-NET)1 111117 11012 1088 18 9973 108...

Forwards rev to schedular exemption,granted by NRC 920320 ltr re testing of emergency condenser condensate return line valves,per 10CFR50,App J.Extension allows worker radiation exposure reductions,detailed in 911212 ltr,to be maintained.

ACCELERATED DISTRIBUTION DEMONSTFWTION SYSTEM~ S .REGULATC INFORNATZON DISTRIBUTION+'STEi4 (RIDE)ACCESSION NBR:9207150054 DOC.DATE: 92/07/09 NOTARIZED: YES DOCKETFACIL:50-,.220 Nine Mile Point Nuclear Station, Unit 1, Niagara Powe 05000220AUTH.NAME AUTHOR AFFILIATIONTERRY,C.D....

Audit Report for KHNP Held from August 19, 2015, through June 20, 2016 Regarding Chapters 4, 6 and 15.

Audit Summary Chapters 4, 6, and 15 of the APR1400 Design Control Document Audit Team: The following NRC staff members participated in substantive discussions during the audit: • Alexandra Burja, NRC Technical Reviewer • Donald Carlson, NRC Technical Reviewer • James Gil...

Final Initial Screening Memo for TDAFW Pump Controls Dec 19.

Tom UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 23, 2014 MEMORANDUM TO: Brian Thomas, Division Director Division of Engineering Office of Nuclear Regulatory Research FROM: Edward O’Donnell, Acting Chief /RA/ E. O’Donnell Re...

Korea Hydro-Nuclear Power Co., Ltd (Design Control Document) - Tier 2 Chapter 09-Auxiliary Systems

APR1400 DESIGN CONTROL DOCUMENT TIER 2 CHAPTER 9 AUXILIARY SYSTEMS APR1400-K-X-FS-13002 REVISION 0 SEPTEMBER 2013  2013 KEPCO and KHNP All Rights Reserved This document was prepared for the design certification application to the U.S. Nuclear Regulatory Commission ...

Korea Hydro and Nuclear Power Co., Ltd - Revised Response to RAI 208-8245 for the Question 03.08.03-1.

03.08.03-1_Rev.1 - 1 / 11 KEPCO/KHNP REVISED 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.: 208-8245 SRP Section: 03.08.03 – Concrete and Steel ...