Regulatory Guide 1.206

Table of Contents/Abbreviation (Document Comparison), to Combined License Applications for Nuclear Power Plants (LWR Edition) (Final)

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Issue date:	06/20/2007
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ii Final Regulatory Guide 1.206 COMBINED LICENSE APPLICATIONS

FOR NUCLEAR POWER PLANTS

(LWR EDITION)

CONTENTS

A.

Introduction B.

Discussion C.

Regulatory Position Section A.

INTRODUCTION ........................................................................................................................-A-

TABLE OF CONTENTS/ABBREVIATIONS................................................................................ Contents B.

DISCUSSION ...............................................................................................................................-B-

C.

REGULATORY POSITION..........................................................................................................

Part I: Standard Format and Content of Combined License Applications for Nuclear Power Plants Light-Water Reactor Edition .................................................

I.1 Introduction and General Description of the Plant

...........................................

C.I.1 I.2 Site Characteristics ........................................................................................... C.I.2 I.3 Design of Structures, Systems, Components, and Equipment I.4 Reactor

..........................

C.I.3 I.4 Reactor .............................................................................................................. C.I.4 I.5 Reactor Coolant and Connecting Systems ........................................................ C.I.5 I.6 Engineered Safety Features ...............................................................................C.I.6 I.7 Instrumentation and Controls ............................................................................C.I.7 I.8 Electric Power ..................................................................................................C.I.8 I.9 Auxiliary Systems .............................................................................................C.I.9 I.10

Steam and Power Conversion System ............................................................. C.I.10

I.11 Radioactive Waste Management .....................................................................C.I.11 I.12 Radiation Protection ........................................................................................C.I.12 I.13 Conduct of Operations ....................................................................................C.I.13 I.14 Verification Programs .....................................................................................C.I.14 I.15 Transient and Accident Analyses ....................................................................C.I.15 I.16 Technical Specifications ................................................................................. C.I.16 I.17 Quality Assurance and Reliability Assurance ................................................. C.I.17 I.18 Human Factors Engineering ............................................................................ C.I.18 I.19 Probabilistic Risk Assessment and Severe Accident Evaluation .................... C.I.19 Part II:

Additional Technical Information

..............................................................................

II.1 Inspections, Tests, Analyses, and Acceptance Criteria.....................................C.II.1 II.2 Environmental Report ...................................................................................... C.II.2 Part III:

Applications Referencing Certified Designs and/or Early Site Permits.....................

iii III.1 Information Needed for a Combined License Application Referencing a Certified Design .............................................................................................. C.III.1 III.2 Information Needed for a Combined License Application Referencing a Certified Design and an Early Site Permit ...................................................

C.III.2 III.3 Finality of an Environmental Impact Statement Associated with an Early Site Permit ..................................................... ........................................................C.III.3 III.4 Combined License Action or Information Items .............................................C.III.4 III.5 Design Acceptance Criteria ............................................................................. C.III.5 III.6 Combined License Application Timing .......................................................... C.III.6 III.7 Inspections, Tests, Analyses, and Acceptance Criteria for Combined License Applications Referencing a Certified Design and/or Early Site Permit ..........C.III.7 Part IV:

Miscellaneous Topics

.............................................................................................

IV.1 Combined License Application Acceptance Review Checklist ......................C.IV.1 IV.2 Submittal Guidance for Combined Licenses ...................................................C.IV.2 IV.3 General Description of Change Processes ...................................................... C.IV.3 IV.4 Operational Programs ...................................................................................... C.IV.4 IV.5 General and Financial Information ................................................................. C.IV.5 IV.6 Limited Work Authorization and Site Redress Plan .......................................C.IV.6 IV.7 Preapplication Activities .................................................................................C.IV.7 IV.8 Generic Issues .................................................................................................C.IV.8 IV.9 Regulatory Treatment of Nonsafety Systems D.

Implementation ..................................................

C.IV.9 D.

IMPLEMENTATION ......................................................................................................-D-

REFERENCES ...............................................................................................................

References

iv Regulatory Guide 1.206 Abbreviations Ci/s micro curies per second Aac alternate alternating current ABWR

advanced boiling-water reactor ac alternating current ACI

American Concrete Institute ADAMS

Agencywide Documents Access and Management System ADS

automatic depressurization system AE

architech-engineer AFW

auxiliary feedwater AFWS

auxiliary feedwater system AISC

American Institute of Steel Construction AL

administrative letter ALARA

as low as reasonably achievable ALI

annual limit on intake ALWR

advanced light-water reactor ANS

American Nuclear Society ANSI

American National Standards Institute AOO

anticipated operational occurrence ASME Code American Society of Mechanical Engineers Boiler and Pressure Vessel Code ASTM

American Society for Testing and Materials ATWS

anticipated transients without scram BE

best estimate BL

bulletin BOL

beginning of life BTP

branch technical position Btu British thermal unit BWR

boiling-water reactor CBP

computer-based procedure CCFP

conditional containment failure probability

v CDF

core damage frequency CFR

Code of Federal Regulations CHRS

containment heat removal system CIV

containment isolation valve COL

combined license COLA

combined license application COL-ITAAC

combined license inspection, test, analysis, and acceptance criteria COSS

computer operated support system CRDM

control rod drive mechanism CRDS

control rod drive system CRE

control room envelope CRHS

control room habitability system CS

core support CSS

containment spray solution CVC

chemical and volume control CVCS

chemical and volume control system d

day D-RAP

design reliability assurance program DAC

design acceptance criteria DAC

derived air concentration DBA

design-basis accident DBE

design-basis event dc direct current DC

design certification DC-ITAAC

design certification inspection, test, analysis, and acceptance criteria DCD

design certification document DCR

design certification rule DCRA

design-centered review approach DCS

data communication system DHS

U.S. Department of Homeland Security DNBW

departure from nucleate boiling ratio DOT

U.S. Department of Transportation EA

environmental assessment

vi EAB

exclusion area boundary EAL

emergency action level EBS

emergency boration system EC

erosion/corrosion ECCS

emergency core cooling system EDG

emergency diesel generator EIS

environmental impact statement EOC

emergency operations center EOF

emergency operations facility EOL

end of life EOP

emergency operating procedure EP

emergency preparedness EP-ITAAC

emergency planning inspection, test, analysis, and acceptance criteria EPA

U.S. Environmental Protection Agency EPIP

emergency planning implementing procedure EPRI

Electric Power Research Institute EPZ

emergency planning zone ER

environmental report ERF

emergency response facility ESBWR

Economic Simplified Boiling-Water Reactor ESF

engineered safety feature ESFAS

engineered safety features actuation system ESP

early site permit ETE

evacuation time estimate F-V

Fussell-Vesely f3 cubic foot FAC

flow-accelerated corrosion or flow-assisted corrosion FDA

Food and Drug Administration FEMA

Federal Emergency Management Agency FHA

fire hazards analysis FHS

fuel handling system FIV

flow-induced vibration FMEA

failure mode and effects analysis

vii FPP

fire protection program FR

Federal Register FR

functional requirement FSAR

final safety analysis report FSER

final safety evaluation report ft foot/feet g/d grams per day GDC

general design criterion/criteria GE

General Electric Co.

GL

generic letter GMRS

ground motion response spectrum GSI

generic safety issue GTG

generic technical guidance GWMS

gaseous waste management systems HA

human action HED

human engineering discrepancy HEPA

high-efficiency particulate air HFE

human factors engineering hr hour HRA

human reliability analysis HSI

human-system interface HSS

high-safety significant HVAC

heating, ventilation, and air conditioning Hz hertz I&C

instrumentation and control IEEE

Institute of Electrical and Electronics Engineers IEEE Std Institute of Electrical and Electronics Engineers standard IGSCC

intergranular stress corrosion cracking IN

information notice in.

inch INPO

Institute of Nuclear Power Operations IOE

industry operating experience ISI

inservice inspection

viii IST

inservice testing ITAAC

inspections, tests, analyses, and acceptance criteria ITP

initial test program kg/yr kilogram(s) per year KI

potassium iodide KIC

fracture toughness data km kilometer KSA

knowledge, skills, and ability kVA

kilovoltampere lb pound LBB

leak before break LCO

limiting condition for operation LCS

local control station LHGR

linear heat generation rate LOCA

loss-of-coolant accident LOOP

loss of offsite power LPZ

low-population zone LWMS

liquid waste management systems LWR

light-water reactor m3 cubic meter(s)

m3/yr cubic meter(s) per year m3/d cubic meter(s) per day Mbq/s Mega-bequerels per second MFCS

main feedwater control system MFW

main feedwater min minute MMI

Modified Mercalli Intensity MOV

motor-operated valve MPa mega pascal MPFF

maintenance-preventable functional failures MR

maintenance rule MRFF

maintenance rule functional failures MSIV

main steam isolation valve

ix MSIVLCS

main steam isolation valve leakage control system MSSS

main steam supply system MWt megawatt thermal NDE

nondestructive examination NDT

nil ductility temperature NEI

Nuclear Energy Institute NOAA

National Oceanic and Atmospheric Administration NPSH

net positive suction head NRC

U.S. Nuclear Regulatory Commission NRO

Office of New Reactors NRR

Office of Nuclear Reactor Regulation NSSS

nuclear steam supply system NUMARC

Nuclear Management and Resources Council OBE

operating-basis earthquake OER

operating experience review OM

operation and maintenance OMB

Office of Management and Budget ORAP

Operational Reliability Assurance Program OSC

operational support center P-STG

plant-specific technical guidelines P-SWG

plant-specific writers guide P&ID

piping and instrumentation diagram PDR

public document room PGP

procedures generation package pH

hydrogen concentration PMF

probable maximum flood PMP

probable maximum precipitation POV

power-operated valve PRA

probabilistic risk assessment PS-ITAAC

physical security ITAAC

PSD

power spectral density PSHA

probabilistic seismic hazard analysis psi pound(s) per square inch

x psid pounds per square inch differential psig pounds per square inch gauge PTS

pressurized thermal shock PWR

pressurized-water reactor PWSCC

primary water stress corrosion crackling QA

quality assurance QAPD

quality assurance program document/quality assurance program description RAP

reliability assurance program RAT

reserve auxiliary transformer RCIC

reactor core isolation cooling RCP

reactor coolant pump RCPB

reactor coolant pressure boundary RCS

reactor coolant system REM

roentgen equivalent man REMP

radiological environmental monitoring program REP

radiological emergency preparedness RFCS

recirculation flow control system RG

regulatory guide RHR

residual heat removal RIS

regulatory issue summary RPV

reactor pressure vessel RQD

rock quality desgination RSS

remote shutdown system RTNSS

regulatory treatment of nonsafety systems RWCS

reactor water cleanup system RWST

refueling water storage tank SAD

software architecture description SAR

safety analysis report SAS

secondary alarm system SAT

systems approach to training SBO

station blackout SDP

significance determination process sec second

xi SECY

Office of the Secretary of the Commission SER

safety evaluation report SGBS

steam generator blowdown system SGI

safeguards information SLCS

standby liquid control system SPDS

safety parameter display system SRM

staff requirements memorandum SRP

standard review plan SRV

safety/relief valve SS-ITAAC

site-specific inspection, test, analysis, and acceptance criteria SSAR

site safety analysis report SSAS

station service air system SSC

structure, system, and component SSE

safe-shutdown earthquake SSI

soil-structure interaction STS

standard technical specification SWMS

solid waste management system T-H

thermal-hydraulic TBD

to be determined TEDE

total effective dose equivalent TGS

turbine generator system TGSCC

transgranular stress-corrosion cracking TMI

Three Mile Island TN

transmission network TS

technical specification TSC

technical support center TSO

transmission system operator TSP

transmission system provider TSTF

Technical Specifications Task Force UHRS

uniform hazard response spectra UHS

ultimate heat sink URD

Utility Requirements Document USGS

U.S. Geological Survey

xii USI

unresolved safety issue v

volt(s)

V/H

vertical to horizontal V&V

verification and validation Vac volt alternating current yr year