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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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LIC-205, Revision 5 "Procedures for NRC's Independent Analysis of Decommissioning Funding Assurance for Operating Nuclear Power Reactors"

U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation NRR OFFICE INSTRUCTION Change Notice Office Instruction No.: LIC-205, Revision 5 Office Instruction Title: Procedures for NRC’s Independent Analysis of Decommissioning Funding Assurance for Operating ...

Luminant - Comanche Peak Units 3 and 4(Final Safety Analysis Report), Rev. 3 - FSAR Chapter 02 Figure 2.4.12-203

Comanche Peak Nuclear Power Plant, Units 3 & 4COL ApplicationPart 2, FSARRevision 3Figure 2.4.12-203 Geologic Map of the CPNPP Vicinity

Luminant - Comanche Peak Units 3 and 4(Final Safety Analysis Report), Rev. 3 - FSAR Chapter 02 Figure 2.5.5-203

Revision 3Comanche Peak Nuclear Power Plant, Units 3 & 4COL ApplicationPart 2, FSARFigure 2.5.5-203 Pre-Construction Cross Section E–E'

Luminant - Comanche Peak Units 3 and 4(Final Safety Analysis Report), Rev. 1 - FSAR Chapter 02 Figure 2.4.2-203

Revision 1Comanche Peak Nuclear Power Plant, Units 3 & 4COL ApplicationPart 2, FSARPFigure 2.4.2-203 PMP Depth Duration Curve

Bellefonte Units 3 & 4 COLA (Final Safety Analysis Report), Rev. 2 - FSAR Chapter 02 Figure 2.4.11-203

Rev 1BLN COL 2.4-3Bellefonte Nuclear Plant, Units 3 & 4COL ApplicationPart 2, FSAR7-Day Low-Flow Frequency CurveFIGURE 2.4.11-203

Luminant - Comanche Peak Units 3 and 4 COLA (FSAR), Rev. 0 - FSAR Chapter 02 Figure 2.4.3-203

Squaw Creek Probable Maximum Precipitation HyetographFIGURE 2.4.3-203 Rev 0COMANCHE PEAK NUCLEAR POWER PLANTUNITS 3 AND 4

2009/07/03-Reply of the State of Nevada to NRC Staff's Answer to Nev-Safety 202 and 203.

  UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Atomic Safety and Licensing Board Before Administrative Judges: ASLBP BOARD 09-892-HLW-CAB04 Thomas S. Moore, Chairman Paul S. Ryerson Richard E. Wardwell In the Matter of ) ) U.S. DEPARTMENT OF ENERGY ) D...

MHI's Responses to US-APWR DCD RAI No. 203-1962, SRP Section: 09.02.01 - Station Service Water System.

AkMITSUBISHI HEAVY INDUSTRIES, LTD.16-5, KONAN 2-CHOME, MINATO-KUTOKYO, JAPANMarch 25, 2009Document Control DeskU.S. Nuclear Regulatory CommissionWashington, DC 20555-0001Attention: Mr. Jeffrey A. CioccoDocket No. 52-021MHI Ref: UAP-HF-09105Subject: MHI's Responses to US-APWR ...

2009/05/15 Areva EPR DC - RE: Response to U.S. EPR Design Certification Application RAI No. 203, FSAR Ch. 6, Supplement 1

1ArevaEPRDCPEm ResourceFrom: Pederson Ronda M (AREVA NP INC) [Ronda.Pederson@areva.com]Sent: Friday, May 15, 2009 11:26 AMTo: Getachew TesfayeCc: BENNETT Kathy A (OFR) (AREVA NP INC); DELANO Karen V (AREVA NP INC); BEELMAN Ronald J (AREVA NP INC)Subject: RE: Response to U.S. E...

Duke Energy WSL III Units 1 & 2 COLA (Final Safety Analysis Report) - FSAR Chapter 03 Figure 3.7-203

NUCLEAR STATION UNITS 1 & 2WILLIAM STATES LEE IIIRepresentative Horizontal Time HistoryFIGURE 3.7-203 Rev 5Representing Unit 1 FIRS

Luminant - Comanche Peak Units 3 and 4(Final Safety Analysis Report), Rev. 1 - FSAR Chapter 02 Figure 2.4.3-203

Revision 1Comanche Peak Nuclear Power Plant, Units 3 & 4COL ApplicationPart 2, FSARFigure 2.4.3-203 Squaw Creek Probable Maximum Precipitation Hyetograph

Luminant - Comanche Peak Units 3 and 4(Final Safety Analysis Report), Rev. 1 - FSAR Chapter 02 Figure 2.4.12-203

Comanche Peak Nuclear Power Plant, Units 3 & 4COL ApplicationPart 2, FSARRevision 1Figure 2.4.12-203 Geologic Map of the CPNPP Vicinity

Email from Y. Faraz to B. Smith re: Phone Call with USEC to Discuss Lic Cond for ACP Intrusion Detection.

From: Yawar FarazTo: Brian SmithDate: 1/31/06 10:59AMSubject: Phone call with USEC to discuss lic cond for ACP intrusion detectionBrian,In a phone call earlier this morning, I asked Kelly Coriell to consider converting the commitmentto provide the final design of the intrusion...

Find Application for Relief Regarding IST of Safety/Relief Valves Acceptable for Review Per LIC-109.

Accession No. ML113081792 From: Feintuch, Karl Sent: Friday, November 04, 2011 5:23 PM To: Browning, Tony; Catron, Steve Cc: Tam, Peter Subject: ME7336 - Relief Request - DUANE ARNOLD - Relief Request VR-02 Regarding In-Service Testing of Safety/Relief Valves - acceptance rev...

Progress Energy Harris Nuclear Units 2 & 3 COLA (Final Safety Analysis Report), Rev. 5 - Chapter 02 - Figure 2.5.1-203

Shearon Harris Nuclear Power Plant Units 2 and 3 COL Application Part 2, Final Safety Analysis Report Rev. 1 Figure 2.5.1-203 has been deleted.

Duke Energy WSL III Units 1 & 2 COLA (Final Safety Analysis Report) - FSAR Chapter 09 Figure 9.2-203

FIGURE 9.2-203 Rev 5Raw Water System,WILLIAM STATES LEE IIINUCLEAR STATION UNITS 1 & 2Make-Up Pond B SubsystemWLS SUP 9.2-5SCREENSINTAKEREFILL STRUCTURE

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. 3 - FSAR Chapter 02 Figure 2.4.1-203

Revision 3Comanche Peak Nuclear Power Plant, Units 3 & 4COL ApplicationPart 2, FSARFigure 2.4.1-203 CPNPP Unit 3 and 4 Intake and Discharge Location Map

Bellefonte Units 3 & 4 COLA (Final Safety Analysis Report), Rev. 3 - FSAR Chapter 02 Figure 2.4.2-203

Rev 3BLN COL 2.4-2Bellefonte Nuclear Plant, Units 3 & 4COL ApplicationPart 2, FSARHMR 56 Local Intense Probable Maximum Precipitation Depth Duration CurveFIGURE 2.4.2-203

Duke Energy WSL III Units 1 & 2 COLA (Final Safety Analysis Report), Rev. 3 - 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 2.5.2-203

Revision 2Comanche Peak Nuclear Power Plant, Units 3 & 4COL ApplicationPart 2, FSARFigure 2.5.2-203 Bechtel Group Contributing EPRI Seismic Source Zones

Luminant - Comanche Peak Units 3 and 4(Final Safety Analysis Report), Rev. 1 - FSAR Chapter 02 Figure 2.3-203

Comanche Peak Nuclear Power Plant, Units 3 & 4COL ApplicationPart 2, FSARRevision 1Figure 2.3-203 National Climatic Data Center Texas Climate Divisions

Issue A to Procedure CP-203, "Clam Shell Filter Blanket Test Fill."

. _ _ _ _ _ . __ _%.:. . . _ _ . _ _ . . . _ . - _ _ . . ... . . . . . . _ . . . . . . _ _ _ . _ . . _ . .4/.i*'.EMSCO SERVICE $ INCORPCMTED'-, .WATORTORD STEAM ELECTRIC STATION - UNIT NO 3PROCEDURE FOR:CIAM SHELL FILTER BIANKET TEST FILL'PROCEDURE NUMBER:'CP-203,"ISSUE SUMMAR...

LER#78-054/03l-0 on 781104:during normal surveillance,while testing MSIV closure time,MSIV 3-203-2A closed 2.8 seconds after initiation signal.Caused by MSIV 3-203-2A valve timing which was out of adjustment.

.. (7·7~y . LICENSEE EVENT REPORT CONTROL BLOCK: I . I '10 .·. (PLEASE PRINT OR TYPE A.EQUIRED INFORMATION_) ~1~..L-~~_.___.~ . ....._---:!6 .. .,. . [illj r I LI DI RI ·s I 3 IG)t o I o I - I o I o I o I o I o I - I o I o 101 4 I 1 I 1 I 1 I 1 101 I 10 7 · 8 9 LICENSEE CODE 1...

Duke Energy WSL III Units 1 & 2 COLA (Final Safety Analysis Report) - FSAR Chapter 02 Figure 2.4.2-203

Rev 2 FIGURE 2.4.2-203Local Intense Probable MaximumWILLIAM STATES LEE IIINUCLEAR STATION UNITS 1 & 2Precipitation Depth-Duration CurveWLS COL 2.4-2Reference Table 2.4.2-203