COMMISSION BRIEFING SLIDES/EXHIBITS

BRIEFING ON RISK-INFORMED,

PERFORMED-BASED REGULATION

AUGUST 2, 2007
US.NRC

UNITED STATES NU1.CLEAR REGULATORY COMMISSION

Protecting People and the Environment

Status of Risk-Informed and

Performance-Based Regulation

for Nuclear Power Plants

August 2, 2007

Gary:Hola.han, PRA Steering Committee

Farouk Eltawila, Nuclear Regulatory Research

Mark Cunningham, Nuclear Reactor Regulation

Charles Ader, New Reactors
Acronym Slide

*ANS

* ASME

American Nuclear Society

- American Society of Mechanical

Engineers

*COL

" EPRI

* LERF

* MOU

* PRA

P PRG

* RPP

- Combined License

Electric Power Research Institute

Large Early Release Frequency

Memorandum of Understanding

- Probabilistic Risk Assessment

-Regulatory Guide

Risk-Informed and Performance-Based Plan

2
Agenda

• Introduction

* PRA quality activities

• Risk-informed activities for oDerating

reactors

° Risk-informed activities for new reactors

* Summary

3
Introduction

* Risk-informed activities since Commission

Briefing of May 2006

* RPP - integrated plan addressing

operating reactors, new reactors,

materials, waste, and security activities

* Communication

PRA Steering Committee

- PRA Leadership Team

- NRC web site

4
PRA Quality Recent

Accomplishments-

* Phased Approach to PRA Quality

* Revision 1 to RG 1.200 and Standard

Review Plan Section 19.1

-Internal fire PRA standard

* Level 1/LERF integrated standard......

• Collaborative -effort with ASME on training

5
PRA Quality Near Te

Activities

* Treatment of Uncertainties

rm

• Revision 2 to RG 1.200

-endorsement of ASME/ANS Integrated

Standard

. PRA training

.- . M D . a a

uxt IGr _____ u _

,Um 4 4 9 4~7 \~

• MOU with EPRI on PRA technical issues

6
Operating Reactors Recent

Accomplishments

* Technical specification initiatives

- Fire protection

* Special. treatment requirements

* Reactor oversight process improvements

7
Operating Reactors Near Term

Activities

° Implementation of fire protection

requirements

* Clarification of maintenance rule PRA

scope

* Emergency core cooling system

requirements

*Pressurized thermal shock

8
New Reactors Recent

Accomplishments

* Revised 10 CFR Part 52

S.Regulatory Guide (RG 1.206) and

Standard Review Plan (Section 19.0)

issued to reflect PRA requirements for

new reactors

- Public meeting held on PRA information to Su- p -pordnl-gign• c-e••Tan

.9
New ,Reactors Near Term

Activities

* PRA reviews for design certification and

COL applications

PRA/risk insights, being used to enhance

staff's review process including:

-Acceptance review'

L.J~~~1I~JE InJ % ==.~LII.j4 dil f A C0114 I UVqzF O

10
Summary

* Steady progress continues to be

accomplished in implementing

Commission PRA policy- and directions

* The new Risk-Informed and PerformanceBased Plan will provide:

-specific objectives and goals in each reaqulatorv arena for achievino Commission ....

-policy and direction

-"enhanced communication via an improved

website

11
Ton~y Pletir ongeO" ~I

Rchard R~se~nLikl~m4'oi~r;aýionaE~o

Mar'Mcurnft South TexSOOqe ~ r 

Greg KUegerr, IExe~loo

August 2, 200

SU CL E AR

E N E R G Y

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Steps forAchieving Enhanced Safety and Reliability
-Nx

R, latory. Q U!ode 1.2001s' o sued addr,Os-0 -Asmpower rn a,

tern; events stand

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10 OFR 5,0.46a 193

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r4E I
Safety•` Benei ofP.

a gul, fflský 00'rmed', Insights, I'd la;,n,,c p -t"'Operat"#oq: -o as "orsa:, -e- a.,nd 'k" A ýh. P- S pflor-Otl v declslo n-" ma, ing an el-, et,'

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:i

Ssto.r.caily, -safetya It's

aS PrR modes iMprvme hav b0e ore by enaee

applications 7.

U O 01PRVpaperý, The afetyf Benebi ~PA reei~

updated at -request of Commission,, demlo'nstrates a`that:,

- Trend of decreasing indu:strywide CI;F is c.o..n.tiuin

- There is a safety and ope~rational benefilt.from, l.ce nsee

applications - I 5,I
CDF vs. Capacity Factor

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IJE: I 1992 1993 1994 1995 1996 1997 1998 1999' 2000 2001 2002 2003 '2004 "2005

YEAR
Industry averageintenati: eve~nts ©I'1IF -.,,ont~iimnUes- ito dl

- quipmen~t pefformnCe.

-6; or VSk ed, "a, nuu.

PR~A mi odet 101,Muenote

-teitfteirltsk OgDnal Usfrnm lmio~edl PRA ol

afflsk 'Informed appraces haebe demntr-dl

ýbotDh safeity andl opervaitionati, rforn i

i'

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Fl'9

ApIrowe a~ UHU1mU\ on~~ WUU 13620,07

- AD~w~ opvators t~ cpt'oan t& exie~ta'id~ x~~

aoed outage. me 6kWr i ~'

-EMST

30- ck 2.'b 

9, o.*nd

IIEIton tu e
Tech Spec In.iti"ative 4Bat8" -STP

Benefits,

Improved safety by maintaini" gfcs o.n rpskignificant "ctvties

-Operational, flex~ibIt

- Fewer chailenges to LCO ACTHION times

oCnducted training on appliicaton ofnewiec•hs

for plant personnel wi•th mphIaSýs on anefec•v÷ •sk

management cuIture

- Operations

- Work Control

- Engineering

Management

*1

o

1
• o.

So'th Texas Project .Perspectiv

• STP has been a Strong proponent and induStry

pioneer of riskinformed appllIcations

Exemption from certain special treatments (50.69-type pilot)

Risk-managed Tech Specs(industry pilot)

- Risk-informed survellance test intervals (submit-by end of '07)

• Risk applications :have enhanced our nuclear safety'•

oversight and strengthened our risk culture

- Ownership resides with implement~ng organizations

- Focus placed on safety slgnificant systems/compone:nts

- Risk considerations woven into fabric of decision-making

S211 :.

NE
South Texas Project Pe rspectiv

* Safety benefits have been complemented by

perforanceim prove ents .-

''

STP's experience showstha ris toolssholr be..

st'rategically implerment ed throughout the, Industry - Efficiencies to be noted in current licensee operations

- Strengthens confidence i;n viab:Ility of new pl'at construction,

* Risk applications are beneficial to safety:

- Clear feedback needed from current Commission on risk

application support

Strategic approach needed to broadly apply beneficial applications

r#4E'

12
-" n a K " -' - ,

Riskop ~naue rn remo~ D

U , E .I.

imer'i,®k tha In, sfy 13Ifor -80 zu yVITsmcs :Ih S<;' @ ,I:FV@• ll @!4)'ellll @ "'

[]Sico) pree ucden • m perlolteme, S .MV.al" c.

onSpeme aproe 8,20 -4R 
- ' "rantra Required, PA If structurefor Sb

Ad='1 PRAinsights are one'Inpu UPt i~n~te raed c.son

*Gap anal-Rgat ysis -to Re~aory.,OuIe. 1.20 an~ AM

PRA standard...

In,. PRAm rod ell.,m ao v , -

* onsidera'blelinvestment 1n0 1'de im oement

(capability and docum e ntatiOn•r) -

E xternal events considered qu~ttv~y(ffi e0

seismic)

fJEI14,
- Work cenvagem"Ryt maaeetsst

-Configuration r!isk

R educed production visk (!lnitilating events

I%1'~ I15
The Changng Role of Ris k

ManagemIenp

* Application of i'kinsights has rgressed at ..

increasing rate during the last 7 years

* In the 90's, the PRA was a tool' applied mostly to

design or engineering programmatic M ssues (Vs Sother rankin applica tons, Ie et c m 

* Today, the PRA is applied 24/7 in operational :

decision-making and support.

r PRA resources stretched to support broad ran e ,of

risk-related regulatory, licensing and operational•

activities 110,

M" E: II I1
Success rPt

*RecogIta of'nuty'n:NC

I ftaStr ~~i

mpoe ats 13 13;

cam,

pro'cas'9

'3 13 13

w Rearj'mtý i ' c expectcato Ons

I!JEI 17

M(L
1,,,nf r'astr uc. ture,

I ndustry PR ifasuc ure 's-saturited, feDv next

years -evera 

RG- 1.20o interaG eveOnts as Sesment tmp 

revisions

- NIFPA 805 fire PRA development

Ongoing applications support activities

- New plant PRA development

*Challenge for NRC ito ral'ntaln SPAR~ mod,- t

*Industry training and pevs'onnean devopmeli

underway,but will take Several years t ch eve ag

numbers of additioal quallfied PRA personnel

18
Capability versus Expectations

*Expectation --

* NRC endorsed standards by 12/2008

SRM states NRC staff may reject or de-prioritnze subittals absent

PRA meeting standards for significant contributors

* Need to heed lessons from internal events standard

development

Internaal events and fire remain industry PRApriority0

and are most significant contributors to manageable

risk

'19
-IIF-6 ACLDF tOh~resho11~di(gvee./"whD!te)A G0 w nimo e~~in v 

bands of

- nue PR reso/lmeson die m, I usk evaGiat6

-mc an, operarng com ai es dil ooURito PO 4ad ito,

Prcs g~oeet'-ewvatd

20''

all

14 I2
Lon developlmon-eflpooda neoedr l

tmerna even'its - awdv an!dl @n~~b

ju~y FederaffRegistei mot@'C)

* ow, Davge a, fot~ tqulkoy devMp 11rfl h_

advace'of stan~d-ar

*PRA endorsement and t'p'ýeMe.tkaýýn~she~ a' Mr

not on sync

1~4E 21
Ouio/Conclusl~o

Near terM focus for hndustry wtry, b:

- At power Internal events PRA:

- Fire PR-A

~.PRAf devGp~m ent IS. a- iý9 Dorg merm ofGi""Ws'olo

' Shouid be tempered by experience atnd Or", Or:es

'~Processes s~houlid focus oln~sft S'On~gi e an~d

not on vesiduaR r•isk Deve:ls

* ndusfty cont~nuess to support O~~13 

RiUsk Infov. md Tech Spec 'U'tia~ve a-pmtoaDs

demonstrate value and sho:Wd be supported] by

Commission

22
PRA - probabillsfc visk a'n~si

o eF Atigating Ssytem a performancelindex

HFNIPA -AIlational ~ePoeto ~~to

EPIRD - MFectwi Power Re~vh' f~tue

El @O ore dama~ge frequen~cy

LC - NH tlng condftioo for operation

MOV mlot'or Operated v~v

C Mule - mainten~ance rule

uSDP - signifcance determinahtion process

a SPAR -Standavdized plant analysis fsk,

23
PRA STANDARDS

DEVELOPMENTS

August 2, 2007

Kenneth R. Balkey, P.E.

Vice President, ASME Nuclear Codes

& Standards

SETTING THE STANDARD
ASME PRA Standard

" ASME RA-S-2002 "Standard For

Probabilistic Risk Assessment For

Nuclear Power Plant Applications"

" Addenda issued to address public

inquiries and NRC staff comments

related to RG 1.200 endorsement

" PRA standards training

~A-,E

-A&G1E 2 SETTING THE STANDARD
ASMEIANS PRA Standard

• Combines ASME/ANS Level 1 standards

" Issue standard with ASME/ANS logo's

• Consistency in format and language

e Provides stability in standard over time

* Allows endorsement of single standard

* Combined standard issued in phases

SETTING THE STANDARD

3
Related Developments

" Applications

- Risk-informed ISI/ IST

- Risk-informed repair / replacement

" New and future reactor initiatives

- Working groups address PRA needs

- Risk-informed safety classification

- Probabilistic design developments

TA TE

SETTING THE sTANDARD 4
Summary

9 ASME has coordinated with NRC

and global industry on risk-informed,

performance-based standards for

over 20 years

e While these standards efforts are

beneficial to stakeholders, they are

long term initiatives

SETTING THE STANDARD