New Reactors: Licensing Basis and Configuration Mgmt Challenges

June 22, 2010 David B. Matthews Director Division of New Reactor Licensing Office of New Reactors

Completion Times for the Current Fleet

Avg = 5.6 yrs Avg = 11.1 yrs 25.0

20.0

15.0

10.0

5.0

0.0

OL Issuance

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10 CFR Part 52 Licensing Processes

• Licensing Processes in 10 CFR Part 52: – Subpart A: Early Site Permit (ESP) • Limited Work Authorization (LWA) under 52.27 and 50.10

– Subpart B: Design Certification (DC) – Subpart C: Combined License (COL) • Provide a predictable licensing process • Resolve safety and environmental issues before authorizing construction • Provide for timely & meaningful public participation • Encourage standardization of nuclear plant designs • Provide regulatory stability to nuclear plant licensees 3

Part 52 - Fitting the Pieces Together

Pre-Construction Construction Verification LWA Early Site Permit Optional Pre-Application Review Combined License Review, Hearing, and Decision Verification of Regulations with ITAAC Reactor Operation Decision Standard Design Certification

• Licensing decisions finalized before major construction begins • Inspections w/ITAAC (Inspections, Tests, Analyses, and Acceptance Criteria) to verify construction • Limited work may be authorized before COL issuance 4

Early Site Permits

• Allows Early Resolution of Siting Issues and “Banking” of a Site for 10 – 20 Years • Review Areas Include: – Site safety – Environmental impact – Emergency preparedness • An applicant for an ESP may concurrently apply for a LWA under 52.27 and 50.10

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Design Certifications

• Allows an applicant to obtain approval of a standard nuclear plant design • Essentially complete design • Final design information • Site design parameters • Interface requirements • Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) 6

Combined License Applications

• Combined construction permit and operating license for a nuclear power plant • May reference an early site permit, a standard design certification, both, or neither • Objective is to resolve all safety & environmental issues before authorizing construction • Prior to fuel load, must verify the facility has been constructed in accordance with the certified design • The combined license process in Part 52 is fundamental for providing regulatory stability for companies building nuclear power plants 7

Completed New Reactor Actions

• 4 Early Site Permits Approved – Clinton, North Anna, Grand Gulf, and Vogtle • 4 Designs Certified – Westinghouse AP600 and AP1000 – GE Advanced Boiling Water Reactor – C-E System 80+ • 1 Limited Work Authorization (LWA) 9

New Reactor Applications Under Review

• 13 Combined License Applications – 18 received, 4 suspended, 1 converted to an ESP application – One includes a 2 nd request for a Limited Work Authorization (Vogtle) • 3 Design Certification (DC) Applications – General Electric Economic and Simplified Boiling Water Reactor (ESBWR) – AREVA U.S. EPR – Mitsubishi U.S. Advanced Pressurized Water Reactor (US APWR) • 1 Amended DC Application – Westinghouse AP1000 Certification Amendment • 1 DC Rule Amendment • 2 ESP Applications 10

One Issue/One Review/One Decision

DC Review Rulemaking Reference COL (RCOL) Subsequent COL 1 (SCOL) Subsequent COL 2 (SCOL) Subsequent COL 3 (SCOL) *The process for a COL includes an opportunity for a contested hearing by the ASLB and also a mandatory hearing that is uncontested before the Commission.

Hearings* Hearings* Hearings* Hearings* 11

Licensing Basis Maintenance Combined License (COL)

NRO/NRC “getting ready” for potential COL issuance Issued a Generic COL (SECY-00-0092, dated April 20, 2000) Preparing update to the Generic COL (SECY in 2010 w/generic license conditions) ISG-11: Licensing Basis Freeze Point

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Potential Post-COL Licensing Actions

•

Combined License process allows for a range of post-COL licensing actions

•

Post-COL License Amendments for:

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Proposed changes to License ( i.e., technical specification changes to include as-built or construction) as-procured information during

–

Proposed changes to

Inspections, Tests, Analyses, and Acceptance Criteria (

ITAAC

)

Design Certifications (DCs) and COLs

•

changes to DC ITAAC also require an exemption under 52.63(b)(1) - Proposed changes to FSAR or Tier 2 that exceed the threshold in the 50.59 or 50.59-like change process

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Post-COL Change Processes

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Changes to and departures from Tier 1 information

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Generic changes to Tier 1 information (DCR - VIII.A.1)

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Departures from Tier 1 require exemptions (DCR – VIII.A.4)

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Changes to and departures from Tier 2 information

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Generic changes to Tier 2 information (DCR - VIII.B.1)

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Departures from Tier 2 information (DCR, VIII.B.5 – 50.59-like)

•

Departures from Tier 2* material require prior NRC approval via a license amendment

–

i.e., new nuclear fuel designs

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Conclusions

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Regulatory processes are in place to handle the expected licensing actions in the near future.

•

NRC is working to address the known workload in FY 2011 and beyond.

•

Early communication with the NRC is important to post-COL licensing actions planning and scheduling for FY 2012 and beyond.

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