ML13268A003

Reactor Decommissioning Process- Presentation for San Onofre 2&3 PSDAR Public Meeting

ML13268A003
Person / Time
Site:	San Onofre
Issue date:	09/25/2013
From:	Camper L NRC/FSME/DWMEP
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Download: ML13268A003 (45)

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The US NRCs Power Reactor Decommissioning Process Larry W. Camper, CIPM CEP Director Division of Waste Management and Environmental Protection Office of Federal and State Material Safety and Environmental Management Programs U.S. Nuclear Regulatory g y Commission 1

Mission

• The NRC licenses and regulates the Nation's civilian use of radioactive materials to protect public health and safety promote the common defense and safety, security, and protect the environment.

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Decommission (10 CFR 20 Subpart E)

To remove (as a facility) safely from service and reduce radioactivity to a level that permits:

1. Release of the p property p y for unrestricted use and termination of the license; or

2. Release of the property under restricted conditions and termination of the license 3

Decommissioning Staff Expertise

- Mechanical Engineers - Environmental Engineers

- Civil Engineers - Environmental Scientists

- Chemical Engineers - Hydrogeologists

- Nuclear Engineers - Geologists

- Geotechnical Engineers - Mathematicians

- Industrial Engineers - Biologists

- Health Physicists - Chemists Over 300 cumulative years of experience 4

Decommissioning Completions 12 10 8

6 4

2 0

Power Reactors RTRs Materials Sites 5

Decommissioned Reactors

- Rancho Seco, 2009

- Big Rock Point, 2007

- Connecticut Yankee Yankee, 2007

- Pathfinder, 2007

- Yankee Rowe, 2007

- Trojan, 2005

- Maine Yankee, 2005

- Saxton, 2005

- Shoreham, 1995

- For Saint Vrain, Vrain 1997

- Shippingport, 1988 6

Key Decommissioning Milestones

• Certification - Permanent Ceasing of Operations Certification - Nuclear Fuel permanently removed from the Reactor

• Post Shutdown Decommissioning Activities Report (PSDAR)

• Decommissioning/Environmental Remediation

• License Li T Termination i ti Pl Plan

• Final Status Survey

• NRC Confirmatory Survey

• Termination/Reduction of Part 50 License 7

Release Criteria

• Unrestricted Release

• Total Effective Dose Equivalent (TEDE) 25 mrem (0.25 mSv/a) and As Low As is Reasonably Achievable (ALARA)

• Averageg member of the critical group g p

• All pathways

• Period of performance - 1000 years

• Restricted release

• 25 mrem (0.25 mSv/a) TEDE and ALARA, with institutional controls in effect

• Legally enforceable institutional controls

• If institutional controls fail, doses do not exceed 1 mSv/a, or 5 mSv/a, under specific circumstances

• Financial assurance - independent third party

• Licensee and NRC public input/outreach requirements 8

Public Meeting Agenda

• NRC Decommissioning Overview

• Reactor Decommissioning Process

• Decommissioning Inspection Program

• Decommissioning Funding

• Spent Fuel Management

• Q&A 9

Public Involvement

• Process Meeting

• Post Shutdown Decommissioning g Activities Report (PSDAR) Meeting

• License Termination Plan Meeting

• Opportunity for Hearing 10

U i d States United S N Nuclear l R Regulatory l C Commission i i The US NRCs Power Po er Reactor Decommissioning Process Bruce A. Watson, CHP C i f Reactor Decommissioning Chief, i i i Branch Office of the Federal, State, Materials Safety and Environmental Protection U.S. Nuclear Regulatory Commission September 26, 26 2013 Carlsbad, California 11

U i d States United S N Nuclear l R Regulatory l C Commission i i NRC Regulations

• 10 CFR Part 20 Subpartp E License Termination Rule was implemented in 1997

• 10 CFR Part 50 - Power Reactor License

• 10 CFR P Partt 72 - Independent I d d t Spent S t Fuel F l Storage Installation License (ISFSI) 12

U i d States United S N Nuclear l R Regulatory l C Commission i i Reactor Decommissioning Options

• DECON: Equipment, structures, etc. removed or decontaminated to a level that p permits radiological g

release

• SAFSTOR: Plant placed in a safe, stable condition andd maintained i t i d in i that th t state t t until til it is i subsequently b tl decontaminated to levels that permits radiological release

• ENTOMB: Plant is encased in a structurally long-lived substance to allow decay until levels permit unrestricted release (not currently available) 13

U i d States United S N Nuclear l R Regulatory l C Commission i i Reactor Decommissioningg - 10 CFR 50.82

• Reactor Decommissioning is required to be completed p in 60 yyears.

• Bases: 50 y in SAFSTOR + 10 y DECON

• Radiation Dose Rates reduced to 1 - 2 %

• Radioactive Waste Volumes reduced to 10%

• Allows Decommissioning Fund to increase

• Coincidently, corresponds well with 20 year life extension for multi-unit sites 14

U i d States United S N Nuclear l R Regulatory l C Commission i i Decision Factors for Licensees in Determiningg the Decommissioning Strategy

• Multi-Unit Site Safetyy

• Financial - Decommissioning Funds Availability

• Access to Radioactive Waste Disposal Capacity

• Future use of the Site

• Stakeholders

• New Business Model

• Special Circumstances 15

U i d States United S N Nuclear l R Regulatory l C Commission i i Power Reactor Decommissioning Process

• Licensee notifies (certifies) NRC within 30 days of permanently ceasing operations

• Certification also required once the fuel has been permanently removed from the reactor vessel

• Licensee submits Post-Shutdown Decommissioning Activities Report (PSDAR) prior to or within 2 years of cessation of operations 16

U i d States United S N Nuclear l R Regulatory l C Commission i i Post Shutdown Decommissioning Activities Report (PSDAR) Contents

• A description p and schedule for the p planned decommissioning activities

• An estimate of the expected decommissioning costs

• A discussion that provides the means for concluding that the environmental impacts associated with the decommissioningg activities will be bounded by appropriately issued Environmental Impact Statements. 17

U i d States United S N Nuclear l R Regulatory l C Commission i i Power Reactor Decommissioning Process

• NRC notices the PSDAR in the Federal Register

• NRC holds a Public Meeting to discuss the PSDAR and solicit comments

• NRC does not approve the PSDAR

• Licensee may begin decommissioning 90 days after NRC receives the PSDAR 18

U i d States United S N Nuclear l R Regulatory l C Commission i i Power Reactor Decommissioning Process

• Licensee performs site decommissioning

• NRC continues to conduct on-site inspections

• Licensee submits License Termination Plan (LTP) at least 2 years prior to requesting license termination

• NRC notices LTP in the Federal Register

• NRC holds a Public Meeting to discuss LTP 19

U i d States United S N Nuclear l R Regulatory l C Commission i i License Termination Plan Contents

• Site radiological characterization information

• Identification of remaining dismantlement activities

• Plans to complete the site remediation

• Detailed plans for the final radiation survey 20

U i d States United S N Nuclear l R Regulatory l C Commission i i License Termination Plan Contents

• A description of the end use of the site, only if restricted release is requested q

• An updated site-specific estimate of remaining decommissioning costs

• A supplement pp to the environmental report p

describing any new information or significant environmental change associated with the licensee's p proposed p termination activities.

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U i d States United S N Nuclear l R Regulatory l C Commission i i Power Reactor Decommissioning Process

• NRC review of the LTP

- Acceptance and Technical Review

- Requests for Additional information, if necessary

- Public Meetings/Opportunity for Hearing 22

U i d States United S N Nuclear l R Regulatory l C Commission i i Power Reactor Decommissioning Process

• NRC approves LTP by amending the license

• Licensee performs remaining decommissioning activities

• NRC performs inspections, including independent p in-process p and confirmatory y surveys to verify licensee survey results 23

U i d States United S N Nuclear l R Regulatory l C Commission i i Power Reactor Decommissioning Process

• Licensee submits Final Status Surveyy Reportp (FSSR)

• NRC performs confirmatory surveys and approves the FSSR

• NRC terminates the license by letter and notices the action in the Federal Register 24

U i d States United S N Nuclear l R Regulatory l C Commission i i SONGS Decommissioning Milestones

• June 7, 2013 - SCE certification of permanent cessation for SONGS Units 2 & 3

• June J 28 2013 - Unit 28, U it 3 defueled d f l d certification tifi ti

• July 22, 2013 - Unit 2 defueled certification

• Deadline for the SONGS PSDAR is June 77, 2015

• Public notice of PSDAR, and public meeting

~60 days after PSDAR submittal

• LTP required within 2 yrs of license termination 25

NRC Inspection Program for Decommissioning Reactors D. Blair Spitzberg, Ph.D., Chief, Fuels Safety & Decommissioning Branch, NRC Region IV Public Meeting on Nuclear Power Reactor Decommissioning Process Carlsbad, California September 26, 2013 26

How to safely get from this to this Connecticut Yankee, CT Maine Yankee, ME Trojan, OR San Onofre Unit 1, CA 27

How o NRCC Ensures su es Sa Safety ety

• Establish and ensure compliance with requirements contained in:

- Regulations

- Safety standards

- License (License Conditions Conditions, Technical Specifications)

• Perform licensing reviews and safety evaluations

• Inspection and enforcement 28

Inspection Activities

• Inspections of Spent Fuel Pool Safety

• Inspections of Decommissioning Activities

- Generally scheduled during periods of higher risk activities

- During and after remediation activities, NRC conducts independent radiological measurements to confirm licensee survey methodologiesg

• Inspections of the Independent Spent Fuel Storage Installation (ISFSI)

• Inspection of Physical Security 29

Objectives of the NRC Inspection Program

• Objectively verify safe conduct of licensee activities

• Verify adequacy of licensee controls

• Ensure safety problems and violations are promptly identified f and corrected and effective actions are taken to prevent recurrence

• Examine trends in licensee safety performance 30

Examples of Core Inspection P

Procedures d for f Decommissioning D i i i

• Organization, Management and Cost Controls

• Safety Reviews, Design Changes and Modifications

• Self Assessments, Audits and Corrective Actions

• Safety of spent fuel

• Occupational Radiation Exposure

• Inspection of Final Surveys

• Radwaste Treatment, Effluent & Environmental Monitoring

• Transportation of Radioactive Material

• Maintenance and Surveillance

• Physical Security

• Contingency response procedures 31

Inspection Planning and Communications

• Routine inspection schedule

- Planned about a year in advance

- Coordinated with the program office in FSME

- Adjustments to schedule made throughout the year as needed

• Inspection planning and execution

- Inspections may be announced or unannounced

- Approved Inspection Plans

- Exit Meetings

• Issue Inspection Report

- 30 day goal for normal inspection reports (post exit)

- 45 day goal for team inspections (post exit)

• Enforcement NRC enforcement policy http://pbadupws.nrc.gov/docs/ML0934/ML093480037.pdf 32

Post ost Inspection spect o Activities ct t es

• Prompt NRC management debrief

• Determination of any significant findings and enforcement

• Issue inspection report Most NRC inspection reports are publicly available.

To locate reports, go to ADAMS web page (http://www.nrc.gov/reading-rm/adams.html), use advanced search feature with docket numbers 05000361, 05000362, and 07200041

• Track and follow up p on safety y issues 33

Decommissioning Funding NRC Requirements &

Expectations Michael Dusaniwskyj Economist Financial Analysis & International Projects Branch Division of Inspection & Regional Support Office of Nuclear Reactor Regulation 34

Decommissioning eco ss o g Funding u d g Assurance ssu a ce NRC regulates Safety not Commerce The NRC has determined that the requirement to provide reasonable assurance of decommissioning g funding g is necessary to ensure the adequate protection of public health and safety. Pursuant to 10 CFR 50.75(b), a reactor licensee is required to provide decommissioning funding assurance by one or more of the methods described in 10 CFR 50.75(e) as determined to be acceptable by the NRC.

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Decommissioning Funding Assurance Decommissioning Funding is an obligation that is taken on when an NRC license is issued The NRC has a comprehensive, p regulation-based g

decommissioning funding oversight program in place to provide reasonable assurance that sufficient funds will be available for decommissioning and radiological decontamination for each US commercial nuclear facility to NRC standards and regulations. (Note: Site restoration or GREEFIELD iis nott under d ththe NRC NRCs jjurisdiction.)

i di ti )

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San O Sa Onofre o e Nuclear uc ea Ge Generating e at g Stat Station o

• Funds are in a dedicated external decommissioning trust

• As of December 31, 2012 trust funds:

• Unit 2 - $1,666,100,000

• Unit U it 3 - $1,890,800,000

$1 890 800 000

• SONGS Unit 1 as of December 31, 2012:

• Remaining trust funds - $295,700,000

• (Est.) remaining costs - $206,500,000 37

NRC REGULATION OF SPENT FUEL AT SAN ONOFRE D. Blair Spitzberg, Ph.D., Chief, Fuels Safety & Decommissioning Branch, NRC Region IV Public Meeting on Nuclear Power Reactor Decommissioning Process Carlsbad, California September 26, 2013 38

Spent Fuel at SONGS

• Spent fuel must have active heat removal in a pool for several years after leaving the operating reactor. After this period, it can be passively cooled by air.

• Spent fuel is being safely stored at San Onofre in fuel pools and in the onsite Independent Spent Fuel Storage Installation (ISFSI).

• Spent fuel pools are able to withstand the same environmental hazard conditions as the reactors, and will be operated by certified fuel handlers who are on shift around the clock.

• Each spent fuel pool has redundant and independent cooling systems, power supplies, pool water sources, and other safety and emergency equipment.

• Both the spent fuel pools and the ISFSI are protected by the San Onofre Physical Security force and its associated security systems. 39

Need for an ISFSI

• The need Th d for f alternatives lt ti tto spentt fuel f l pooll storage emerged in the 1970s.

• The Nuclear Waste Policy Act of 1982 and Amendments Act of 1987 laid out a process for licensing a geological repository.

• A geologic repository is still decades away

• Dry cask storage was developed to meet the need for expanded onsite storage of spent fuel due to the lack of a national repository available for use use.

• SONGS ISFSI became operational in October 2003.

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U.S. Independent Spent Fuel Storage Installations Trojan Columbia 1

Big Rock Point Monticell Nine Mile Pt o

Kewaunee Fitzpatrick 3 2 DOE TMI-2 Storage 4

Humboldt Bay Prairie Island LaCrosse DOE Idaho Spent Fuel Facility Ginna 5 Point Beach 6 Palisades Fermi Perr 8 7 Zio 9 n y Cook Davis Northeast:

6 5 11 1. Maine Yankee Besse 10 13 7 1 14 2. Seabrook Ft. Calhoun Rancho Seco Ft Saint Vrain (vault 4 2 Beaver 3. Vermont Yankee 12 1 Private Fuel Storage storage) 3 Valley y 4. Yankee Rowe Midwest: 5

1. Dresden 5. Pilgrim Coope 8 North 16

2. GE Morris (wet) 6. Haddam Neck r Anna 7. Millstone

3. Braidwood

4. LaSalle Surry 8. Indian Point

5. Byron 9. Susquehanna

6. Duane Arnold 10.Three Mile Island Callaway

7. Quad Cities 11. Limerick Wolf Creek 8. Clinton 12. Peach Bottom Shearon Harris McGuire 13. Oyster Creek Diablo Canyon 14. Hope Creek Watts 15 Salem 15.

C t b Catawba Bar 16. Calvert Cliffs Sequoya Oconee h Robinson Brunswick San Browns Arkansas Nuclear Ferry Summer Onofre Palo Verde One Vogtle Current as of February 2013: Hatch Farle 54 Operating General Licensed ISFSIs at Reactor Sites Comanche Peak Grand y

Gulf 9 Reactor Sites Pursuing a General licensed ISFSI River Bend Crystal River Waterford South Texas St. Lucie Project 5 Reactor sites have not announced intentions regarding ISFSI Turkey Point 33 States have at least one ISFSI Railroads Interstate Highways Disclaimer: This map provides only general information regarding the current and potential ISFSI licensees, based on various information sources that may be inexact. The map will be updated 41 when changes occur.

SONGS ISFSI Dry Shielded Canister Horizontal Storage Module under construction

• SONGS uses the Transnuclear Advanced NUHOMS Horizontal Modular Storage System.

• Major components are the Dry Shielded Canister (DSC) and the Horizontal Storage Module (HSM).

• Each DSC has an outer shell consisting of 5/8 inch thick stainless steel with steel internal spacer discs.

• The DSC has a welded internal confinement boundary and separate welded lid.

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SONGS ISFSI

• The DSC is placed horizontally inside each AHSM module, into a steel support pp structure.

• The AHSM has thick steel reinforced concrete walls (>4 feet thick) and roof slabs (~5 feet thick) which provide additional structural p protection to the canister and radiation shielding.

g

• The ISFSI pads are steel reinforced concrete with a minimum thickness of 3 feet. 43

SONGS ISFSI Seismic Designg Considerations

• The SONGS ISFSI is designed for high seismicity sites.

• The Design Basis Earthquake (DBE) used to analyze the SONGS ISFSI is 2.24 times higher than that used in the licensing of the San Onofre reactors.

Flooding/Tsunami Considerations

• The SONGS ISFSI is located 19.75 feet above sea level.

• The maximum flood condition of 29 feet was evaluated for the ISFSI which would potentially put the ISFSI pad under 9 feet under water. The design basis flood for the AHSM design is to withstand a submersion of 50 feet of water.

• The maximum tsunami, including storm height of the waves was evaluated at 27 feet for the SONGS ISFSI. This is less than the maximum flood conditions evaluated e a ua ed for o thee ssite.

e

• All evaluations do not take credit for the 28 foot tall sea wall which exist between the ocean and ISFSI.

• If the ISFSI were to get temporarily flooded during a tsunami, no adverse thermal effects would occur.

occur 44

Inspection of Spent Fuel Storage Spent Fuel Pool inspection

• Inspections of spent fuel pool safety will continue semi-annually using Inspection Procedure 60801 - Spent Fuel Pool Safety at Permanently Shutdown Reactors.

ISFSI inspection

• Routine ISFSI inspections are normally performed every 2 years following guidance contained in NRC Manual Chapter 2690 Inspection Program for Dry Storage of Spent Reactor Fuel at Independent Spent Fuel Storage Installations and For 10 CFR Part 71 Transportation Packaging.

• This Manual Chapter references the Inspection Procedures to be implemented implemented.

• NRC attempts to schedule routine inspections during ongoing cask loading operations.

How to find NRC inspection guidance and reports

• NRC inspection guidance can be found on the NRCs website at http://www.nrc.gov/reading-rm/doc-collections/#insm

• Most NRC inspection reports are publicly available. To locate reports, go to ADAMS web page (http://www.nrc.gov/reading-rm/adams.html),

(http://www.nrc.gov/reading rm/adams.html), use advanced search feature with docket numbers 05000361, 05000362, and 07200041.

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