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Duke Energy WSL III Units 1 & 2 COLA (Final Safety Analysis Report) - FSAR Chapter 02 Figure 2.4.1-203

NUCLEAR STATION UNITS 1 & 2WILLIAM STATES LEE IIIPhysiographic and HydrogeologicFIGURE 2.4.1-203 Rev 0Provinces of South Carolina WLS COL 2.4-1Source: Reference 267

Luminant - Comanche Peak Units 3 and 4(Final Safety Analysis Report), Rev. 2 - FSAR Chapter 02 Figure 2.5.4-203

Revision 2Comanche Peak Nuclear Power Plant, Units 3 & 4COL ApplicationPart 2, FSAR Figure 2.5.4-203 Suspension Log Borings and Engineering Cross Section Locations

Duke Energy WSL III Units 1 & 2 COLA (Final Safety Analysis Report), Rev. 2 - FSAR Chapter 02 Figure 2.4.1-203

NUCLEAR STATION UNITS 1 & 2WILLIAM STATES LEE IIIPhysiographic and HydrogeologicFIGURE 2.4.1-203 Rev 0Provinces of South Carolina WLS COL 2.4-1Source: Reference 267

Progress Energy Levy Units 1 and 2 COLA (Final Safety Analysis Report), Rev. 7 - Chapter 02 - Figure 2.5.4.8-203

FIGURE 2.5.4.8-203����������������Rev. �����������������������������������������������Turbine Building Subgrade��Duke Energy Florida Levy Nuclear Plant Units 1 and 2 Part 2, Final Safety Analysis Report

Ltr contract:mod 5 to task order 12 under contract NRC-33-92-203.

' - - ---- - - - ---"fh f). .n, . .# "8 %,UtJITED STA1LS%,:. -#! j jNUCLEAR REGULATORY COMMISSIONwAsmotou, o.c. mm *j,\ .... /t!:' ; , M?,'Applied Management Systems, Inc.ATTH: Margaret Hutchison6116 Executive BoulevardSuite 440Rockville, Maryland 20852Dear Ms. Hutchison:Subje...

Staff requirements memo re affirmation session on 980826 in Rockville,MD concerning SECY-98-203.

.o ,-........................;aurg|RELEASED TOTHE PDR*---- UNITED STATES*.ANUCLEAR REGULATORY COMMISSION |'?jpgJk| ogWASHINGTON, D.C. 20555-0001- .[August 26, 1998N dM M k($/N ******'**.** REFER TO: M980826COFFICE OF THESECRETARYMEMORANDUM FOR: John F. Cordes,- Acting Director...

Progress Energy Levy Units 1 and 2 COLA (Final Safety Analysis Report), Rev. 6 - Chapter 02 - Figure 2.5.4.5-203

Levy Nuclear Plant Units 1 and 2 Part 2, Final Safety Analysis Report Diaphragm Wall With Prestressed AnchorsRev �����������������������Levy Nuclear Plant Units 1 and 2 Part 2, Final Safety Analysis ReportFIGURE 2.5.4.5-203

Responds to violations noted in Insp Rept 50-302/86-21. Corrective actions:reactor operators evaluated & Procedure TDP-203 revised to clarify simulator evaluation requirements.

sMtQ'.e....oOo ,I,*. o.s' 00I |11|g ,. , yFloridaPowerC O R PO R ATIO NSeptember 26, 19863F0986-26Dr. J. Nelson GraceRegional Administrator, Region IIOffice of Inspection and EnforcementU.S. Nuclear Regulatory Comission101 Marietta Street N.W., Suite 2900Atlanta, GA 30323Subje...

2008/11/06 - Comment (203) E-mail regarding Uranium Recovery draft GEIS

1URGEISCEmailsFrom: GLORIA DIMICCO [TLCPETS@PTD.NET]Sent: Thursday, November 06, 2008 10:23 AMTo: NRCREP ResourceSubject: Uranium Recovery GEIS Dear Mr. Park, I am writing to you to ask that the NRC follow the National Environmental Protection Act (NEPA) and conduct individua...

2009/03/12 Areva EPR DC - Draft - U.S. EPR Design Certification Application RAI No. 203 (2253_2276), FSAR Ch. 6

1ArevaEPRDCPEm ResourceFrom: Getachew TesfayeSent: Thursday, March 12, 2009 7:38 PMTo: 'usepr@areva.com'Cc: Jeffrey Poehler; David Terao; Walton Jensen; Christopher Jackson; Michael Miernicki; Joseph Colaccino; ArevaEPRDCPEm ResourceSubject: Draft - U.S. EPR Design Certificati...

Westinghouse Electric Company Response To U.S. Nuclear Regulatory Commission (NRC) Inspection Report [05200006/2010-203] and Notice of Violation.

November 23, 2010 Mr. R. F. Ziesing, Director U.S. Licensing, Nuclear Power Plants Westinghouse Electric Company 1000 Westinghouse Drive, Suite 115 Cranberry Township, PA 16066 SUBJECT: WESTINGHOUSE ELECTRIC COMPANY RESPONSE TO U.S. NUCLEAR REGULATORY COMMISSION (NRC) I...

Ltr contract,mod 8 to task order 11 under contract NRC-33-92-203.

e .PCD#.& %,g 3- UNITED STATESO -SNUCLEAR REGULATORY COMMISSIONfWASHINGTON. D.C. 20066-0001%,W Y 0 9 1997iApplied Management Systems, Inc.>> ATTN: Margaret Hutchison6116 Executive BoulevardSuite 440-Rockville, Maryland 20852Dear Ms. Hutchison:Subject: Modif.ication No. 08 to T...

Bell Laboratories, Termination Request Letter dated 01/25/2006. Requests Termination of Licenses SMB-1260 & SNM-203.

Bell Labs Innovations for Lucent Technologies January 25,2006 United States Nuclear Regulatory Commission Nuclear Materials Safety Branch Division of Nuclear Materials Safety Region 1 475 Allendale Road King of Prussia, PA 19406 " Re: Termination of Licenses SMB- 1260 SNM-203 ...

Duane Arnold Energy Center, Correction to Amendment 203 re: omitted TS page.

Mr. Lee Liu Chairman of the Board and Chief Executive Officer IES Utilities Inc. P. 0. Box 351 Cedar Rapids, IA 52406December 13, 1994 Distribution Docket File PUBLIC PD3-3 r/f JRoe JMedoff GHammer RFrahm RPulisfer JMinns WLaFavew/encl: GHill (2) OGC CGrimes ACRS (4) EGreenma...

Dresden Nuclear Power Station, Units 2 and 3, Submittal of Information to Fast Closure Time of the 203-1C Inboard Main Steam Isolation Valve.

e ' • Commonwealth Edisori d;,~Pany Fil& Cy. 72 WEST ADAMS STREET * CHICAGO, ILLINOIS Addt.., Reply to, POST OFFICE BOX 767 *CHICAGO, ILLINOIS 60690 Dr. Peter A. Morris, Director Division of Reactor Licensing U.S. Atomic Energy Commission Washington, D.C. 20545 R. R. 111 Morri...

IR 99900404-13-203, On 04/03-05/2013, Westinghouse Electric Company Nuclear Services, & Notice of Nonconformance.

June 14, 2013 Mr. William Bedont, Resource Manager Westinghouse Electric Company Nuclear Services P.O. Box 158 – Waltz Mill Site Madison, PA 15663 SUBJECT: NUCLEAR REGULATORY COMMISSION INSPECTION REPORT NO. 99900404/2013-203, NOTICE OF NONCONFORMANCE Dear Mr....

Pilgrim Nuclear Power Station / Completion of Review of Engineering Evaluation for Leaking Safety Relief Valve SRV-203-3B (Tac No. MA0874)

February 21, 2001Mr. Mike BellamySite Vice PresidentEntergy Nuclear Generation CompanyPilgrim Nuclear Power Station600 Rocky Hill RoadPlymouth, MA 02360SUBJECT: COMPLETION OF REVIEW OF ENGINEERING EVALUATION FOR LEAKINGSAFETY RELIEF VALVE SRV-203-3B AT THE PILGRIM NUCLEAR POWE...

RESPONSE TO NOTICE OF VIOLATION (NRC SPECIAL INSPECTION REPORT NOS. 50-186/2000-202 AND 50-186-203)

December 1, 2000Dr. Edward A. Deutsch, DirectorResearch Reactor CenterUniversity of Missouri-ColumbiaResearch ParkColumbia, MO 65211SUBJECT: RESPONSE TO NOTICE OF VIOLATION (NRC SPECIAL INSPECTIONREPORT NOS. 50-186/2000-202 AND 50-186/2000-203)Dear Dr. Deutsch:Thank you for yo...

Telecopy RO:on 720619,automatic pressure release valve 203-3-D failed to operate.Investigation in progress.

. .a1,_a. . . - ,|-mas sat7 .Telegram'-l4 tuestem uninn--;. .... ,-w... .. . .. ...419P EST JUN 19 72 DEB 719 ... m0450P EDT06/19/720SSB221 DE CCE205 (SF 171CC501pI5)PD WU TSDEPT MOLI3/L 9bj2C2C 2 PD TDMS CORDOV A ILL 19 337P CDTg6DUANE BOYD REC 3 COMPLIANCE-37 f j

Proposed amends 203 & 161 to licenses NPF-14 & NPF-22, revising improved std tech specs.

BEFORE THEUNITED STATES NUCLEAR REGULATORYCOMMISSIONIn the Matter ofPPAL, INC.Docket No. 50-388REVISION TO PROPOSED AMENDMENTNO. 161FACILITYOPERATING LICENSE NO. NPF-22SUSQUEHANNA STEAM ELECTRIC STATIONUNITNO. 2Licensee, PPAL, Inc., hereby files a revision to proposed Amendmen...

Notice of Expiration of Highway Route to Transport Spent Nuclear Fuel from Oconee, Seneca, SC, to the United States/Canadian Border (NRC Route 203).

April 4, 2005Mr. Julio Raffo, Director of OperationsEdlow International Company1666 Connecticut Ave., N.W., Suite 201Washington, D.C. 20009SUBJECT: NOTICE OF EXPIRATION OF HIGHWAY ROUTE TO TRANSPORT SPENTNUCLEAR FUEL FROM OCONEE, SENECA, SC, TO THE UNITEDSTATES/CANADIAN BORDE...

Issuance of Amendment No. 203 for Three Mile Island Nuclear Station, Unit No 1 DPR-50

August 27, 1997Mr. James W. Langenbach, Vice President and Director, TMI GPU Nuclear Corporation P.O. Box 480 Middletown, PA 17057 SUBJECT: THREE MILE ISLAND - ISSUANCE OF AMENDMENT RE: THE CORE FLOOD TANK VOLUME, HIGH PRESSURE INJECTION PUMP FLOWRATE, AND DECAY HEAT SYSTEM VA...

Progress Energy Levy Units 1 and 2 COLA (Final Safety Analysis Report), Rev. 7 - Chapter 02 - Figure 2.4.2-203

LNP COL 2.4-2Rev 6Levy Nuclear PlantUnits 1 and 2Part 2, Final Safety Analysis ReportDuke Energy FloridaLocal Intense Probable Maximum Precipitation Intensity-Duration CurveFIGURE 2.4.2-203 010203040506070800 3 6 9 12 15 18 21 24Duration (hr)Intensity (in./hr)NU042008001TPA L...

Progress Energy Levy Units 1 and 2 COLA (Final Safety Analysis Report), Rev. 1 - Chapter 02 - Figure 2.4.6-203

FIGURE 2.4.6-203 Rev 0Progress Energy FloridaLNP COL 2.4-2Generalized Neotectonic Featuresof the Caribbean Region Levy Nuclear PlantUnits 1 and 2 Part 2, Final Safety Analysis ReportSource: McCann, W.R., 2004Notes:CI - Cayman IslandsPAP - Port-au-PrinceSD - Santo DomingoCV - ...

S. Penrod Ltr. Ref: Response To Disputed Violations 70-7001/2006-203-01 And -02 Regarding The Failure To Report A Loss Of Double Contingency To The NRC.

February 26, 2007EA-07-323Mr. Steven R. PenrodGeneral ManagerPaducah Gaseous Diffusion Plant P.O. Box 1410Paducah, KY 42002SUBJECT: RESPONSE TO DISPUTED VIOLATIONS 70-7001/2006-203-01 AND -02REGARDING THE FAILURE TO REPORT A LOSS OF DOUBLECONTINGENCY TO THE NRCDear Mr. Penrod:...