Plant Parameter Envelope: Concept and Application for

OPG New Nuclear at Darlington

Presentation to the CNSC

Jack Vecchiarelli Section Manager, Safety Analysis

Darlington New Nuclear Project

December 9, 2009

2

To brief CNSC staff on the Plant Parameter Envelope (PPE) concept and its licensing application for the OPG New Nuclear at Darlington project

Purpose of Presentation

3

IntroductionBackground on PPE Concept (origin, etc.)Use of PPE

PPE Development ProcessOrganization of PPESummary of PPE

Site ParametersDesign Parameters

• Reactor Class Specific Parameters• Vendor Design Specific Parameters

Conclusion

Outline

4

The PPE is a tabular set of data that:

-relates to the interaction between a nuclear power plant and the site/environment

-provides a bounding envelope of plant design and site parameter values for use in the Licence To Prepare Site (LTPS) Application and Environmental Assessment (EA)

-is derived from available vendor information for multiple reactor designs

Introduction

5

5

Background

PPE approach was proposed in U.S. by Nuclear Energy Institute (NEI) to allow utilities to apply for Early Site Permits (ESP) before committing to a particular design

-ESP is analogous to Canadian site preparation licence

PPE approach has been accepted by US NRC

Used successfully by 3 U.S. utilities in obtaining ESPs:-Dominion Nuclear (North Anna site)

ESP issued November 2007

-Energy Resources Inc. (Grand Gulf site) ESP issued April 2007

-Exelon Generation Company (Clinton site) ESP issued March 2007

6 Use of PPE (1)

The PPE is used in support of the LTPS Application and EA for the OPG New Nuclear at Darlington project – before a design has been selected-evaluation of impact of plant on environment

-part of EA bounding framework

-part of exclusion zone determination

-evaluation of impact of site on plant

-site evaluation to support suitability of the site for a new build

PPE provides high-level design information consistent with CNSC INFO-0756 and RD-346 requirements

7 Use of PPE (2)

The PPE defines part of the licensing boundary/basis

-PPE is a living document which OPG will maintain

With the LTPS Application, PPE is used to demonstrate site is suitable for construction of a Nuclear Facility as bounded by the PPE

If the selected Nuclear Facility is not bounded by the PPE, the PPE will be updated and appropriate assessment of the impacts will be undertaken as required

-addressed during the more detailed design stages of the licensing process, i.e., Construction License Application

8 OPG PPE Development Process

9Development of the PPE for the

OPG New Nuclear at Darlington Project

Candesco provides draft. OPG sends PPE to vendors. AECL, Areva and GE confirm designs bounded.

Jan 2008

PPE Rev 2 submitted with LTPS Application.Sep 2009

PPE Rev 2 issued by OPG – approved by CNE.Mar 2009

PPE Rev 1 submitted to CNSC. OPG begins PPE update for Vendor Specific Design parameters.

Oct 2008

PPE Rev 1 issued by OPG – approved by CNE.Aug 2008

AECL, Areva, Westinghouse reply. PPE Rev 1 prepared. Jul 2008

OPG sends Draft PPE Rev 1 to 3 vendors.Jun 2008

PPE Rev 0 issued by OPG – approved by CNE. IO RFP issued. Three responses. OPG begins revision of PPE.

Apr 2008

OPG arranges for Independent Peer Review of draft PPE Rev 0.Feb 2008

Contractor (Candesco) analyzes data per its QA program.Aug 2007

Vendors provide data per their QA program.Jul 2007

OPG requests data on 9 designs.Jun 2007

10 Limiting Value Determination

The PPE is based on limiting values – the value for each parameter that describes the greatest impact of the plant on the site/environment, or of the site on the plant

the maximum or minimum from the set of vendor values for a given parameter, as appropriate, chosen conservatively

ACR-1000 AP1000 EPR3000 Pa 3591 Pa 4788 Pa

ACR-1000 AP1000 EPR-31.2 C -40 C -40 C

Limiting Minimum Value: Snow & Ice Load

Limiting Maximum Value: Min. Amb.Temp. for full power operation

11 Organization of the PPE

To consider multiple units on site, the PPE includes prorated values for Reactor Class Specific and Vendor Design Specific parameters.

12 Summary of PPE Tables

Site Parameters – 39 parameters related to the impact of the site on the plant, as assumed in the plant designs

Examples: snow load, earthquakes, design basis tornado

Reactor Class Specific (RCS) – 127 parameters that are similar within each reactor class (PWR, PHR)

Examples: fuel enrichment, total mass of zirconium alloy in core, heaviest construction shipment

Some RCS parameters were added by OPG to those adopted from NEI list

Vendor Design Specific – 35 parameters which address radiological effects due to nuclear fuel

Examples: Airborne effluent, liquid radwaste, solid radwaste

13 Sample PPE Values and Usage

Aquatic Environment Assessment of Environmental Effects TSD NND EA, Section 2.2.1, Project Basis for Assessment, page 2-2

228,400 L/s

(4 ACR-1000)

2.6.2 Cooling Water Flow Rate (once-through cooling)

Exclusion Zone Determination for Darlington New Nuclear Project

Section 4.0 Conclusions

3 EPR

4 AP1000

4 ACR-1000

(Table 2) Number of Reactor Units On Site

Site Evaluation of the OPG New Nuclear at Darlington – Part 6: Evaluation of Geotechnical Aspects

Section 5.1, Table 5.1-1 – “Site Parameters – Composite Table” (Relevant to Geotechnical Aspects)

718 kPa

(EPR)

1.5.2 Minimum Required Bearing Capacity (Static) – Soil Property

Site Evaluation of the OPG New Nuclear at Darlington – Part 2: Dispersion of Radioactive Materials In Air and Water

Section 3.1, Table 3.1-2 – Airborne Release Parameters (for estimation of public dose due to normal operation)

71.3 m

(AP1000)

1.1.1 Building Height

Where UsedValueParameter

14 Sample Site Parameters

EPR8274 PaDBT max pressure drop

ACR-100046 mDBT radius of maximum rotational speed

EPR368 km/hDesign Basis Tornado (DBT) max wind speed

EPR, AP1000232 km/hBasic wind speed

EPR-1 mMaximum ground water

EPR, AP1000, ACR-1000

0.3 gPeak ground acceleration

ACR-10003000 PaSnow and ice load

ACR-1000400 mm/d

100 mm/h

30 mm/15 min

Maximum rain fall rate

Limiting Reactor Limiting ValueParameter

15Sample Reactor Class Specific Parameters:

Plant Characteristics

13.5 mEPR12.7 mFoundation Embedment

65.8 mAP100071.3 mBuilding Height

60 yearsAll60 yearsDesign Life

>95% annual

>90% lifetime

EPR94%Capacity Factor

3200 MWEPR4590 MWThermal Power

1165 MW gross

1085 MW net

EPR1708 MWElectrical Output

PHR

(ACR-1000)

PWR Limiting Reactor

PWR Limiting Value

Parameter

16Sample Reactor Class Specific Parameters:

Fuel

5246

metric tons

EPR2712

metric tons

Total mass, discharged fuel

15

metric tons

EPR43

metric tons

Mass of zirconium alloys in core

115

metric tons

EPR146.26

metric tons

Mass of fuel in core

2.5%EPR5% Fuel enrichment

PHR

(ACR-1000)

PWR Limiting Reactor

PWR Limiting ValueParameter

17Sample Reactor Class Specific Parameters:

Construction

2000 to 2500EPR4200Construction population

32.9 acres EPR12.6 acresLaydown area

422 metric tons (on land)

1600 metric tons (by water)

800 metric tons(calandria)

AP-1000861.8 metric tonsHeaviest construction shipment

Length 17.37 m

Width 10.1 m

Height 10.45 m

Longest item Length 40 m

AP-1000Length 28.35 m

Width 25 m

Height 27.43 m

Diam. 39.62 m

Module dimensions

PHR

(ACR-1000)

PWR Limiting Reactor

PWR Limiting valueParameter

18Sample Reactor Class Specific Parameters:

Decommissioning

92,000 (Qty: 4)

52,600 (Qty: 4)

5,380 (Qty: 4)

21,280 (Qty: 4)

1,600

10.5 m H 17.4 m L 10.1 m W

PHR (ACR-1000)

EPR (Qty: 3)

540,000Mass non-active material (T)

EPR (Qty: 3)

45,000Mass low active material (T)

EPR (Qty: 3)

2700Mass moderately active material (T)

EPR (Qty: 3)

2,400Mass highly active material (T)

EPR350Heaviest shipment metric tons (T)

EPR25 m long 7 m diam.

Decommissioning dimensions, Largest

PWR Limiting Reactor

PWR Limiting Value

Parameter

19Sample Vendor Design Specific Parameters:

Normal Operating Source Term

2.1×1010 Bq/y9.46×109 Bq/y7.15×109 Bq/yLiquid source term

1.2×1014 Bq/y3.74×1013 Bq/y6.14×1013 Bq/yLiquid H-3 source term

5.0×1013 Bq/y1.295×1013 Bq/y6.67×1012 Bq/yGaseous H-3 emission

5.9×1013 Bq/y4.08×1014 Bq/y1.77×1015 Bq/yNormal gaseous emission source term

ACR-1000AP-1000EPRParameter

20 Conclusions

The PPE provides bounding values based on multiple vendor technologies

helps define the bounding conditions for EA purposes

facilitates robust evaluations before a reactor design has been selected

consistent with other jurisdictions (e.g. U.S.)

As such, the PPE is used by OPG to support the EA and the LTPS Application for the OPG New Nuclear at Darlington project

is a living document which OPG will maintain

represents licensing limits within a modern regulatory framework that features built-in margins

will be used to confirm selected technology is bounded by present/updated evaluations

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Canadian Nuclear Commission canadienne Safety Commission de sûreté nucléaire

P.O. Box 1046 Station B 280 Slater Street Ottawa, Ontario Canada K1P 5S9

C.P. 1046 Succursale B 280, rue Slater Ottawa (Ontario) Canada K1P 5S9

Meeting SummaryE-Docs #3472463: File/Dossier:2.01

CEAR #: 07-05-29525Date: December 9, 2009

SUBJECT OBJET

CNSC Meeting with OPG – Plant Parameter Envelope: Concept and

Application for OPG New Nuclear at Darlington

ATTENDEES

PARTICIPANTS

CNSC Marcel De Vos Barclay Howden Andrew McAllister Julie Mecke Dave Newland Doug Miller Garry Schwarz Sang Shim Ross Richardson

OPG Leslie Mitchell Jack Vecchiarelli

CEAA Jill Adams Robyn-Lynne Virtue (by teleconference)

LOCATION OF MEETING

ENDROIT DE LA RÉUNION

Canadian Nuclear Safety Commission 280 Slater Street, Ottawa (Ontario)

(Room #03-070)

DATE December 9th, 2009

TIME/HEURE 9:00 am – 11:30 am

REMARKS

REMARQUES

1. Meeting Purpose

Leslie Mitchell (OPG): Provided context for the purpose of the meeting, which was to brief CNSC and CEAA staff on the Plant Parameter Envelope (PPE) concept and its application in the Environmental Impact Statement (EIS) and Licence to Prepare Site (LTPS) Application for the OPG New Nuclear at Darlington Project.

2. OPG Presentation Jack Vecchiarelli (OPG): Presented the PPE Concept and Application for OPG New Nuclear at Darlington (see E-doc 3472460 for OPG Presentation). OPG clarified that Revisions 0, 1, and 2 of the PPE were approved by the Chief Engineer for the New Nuclear at Darlington project.

3. CNSC/CEAA Staff Discussion Points

CNSC and CEAA staff raised a number of discussion points during the OPG presentation. These points are summarized as follows:

• OPGs confidence in the PPE data provided by the reactor vendors.

• Linkages between the PPE data and its usage in the EIS and LTPS Application.

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• Linkages between site parameters provided in the PPE and the site characteristics provided in the site evaluation studies.

• Consistency in information presented in the PPE versus information presented in the EIS and LTPS Application.

• Differences between OPG’s PPE approach and USNRCs accepted PPE approach for Early Site Permit (ESP) Applications.

CNSC and CEAA staff indicated that further questions on the PPE concept may be raised as proposed Information Requests to the Darlington Joint Review Panel.

Staff also indicated that the other members of the Federal Review Team would benefit from receiving a similar presentation by OPG. OPG agreed in principle to provide this presentation to the Federal Review Team in early 2010.

NOTES WRITTEN BY

Name(s)/Nom(s) : Ross Richardson/Melanie Mallette