ML042090371
| ML042090371 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 07/15/2004 |
| From: | NRC Region 1 |
| To: | |
| References | |
| Download: ML042090371 (7) | |
Text
NRC Public Meeting Spent Fuel Storage at Indian Point July 15,2004 Peekskill, NY 11 NRC Speakers Chip Cameron, Facilitator Office of the General Council Brian Holian, Deputy Director Division ol Reactor Prolects Region 1 Larry Camper, Deputy Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Dr. Ron Beiiamy, Chiel Projects Branch 6 Licensing Section Division of Reaclor Projects Region 1 John Monninger, Chief Spent Fuel Project Oflice Office of Nuclear Material Salely and Safeguards 5
Overview Annual Assessment Meeting Summary Recent Emergency Exercise Current Plant Performance Indian Point ISFSI Overview I
2 Agenda Welcome Opening Remarks Presentation Requirements for Dry Cask Storage
- Licensing of Dry Cask Storage Systems
- inspection of Dry Caskstorage Systems Questions and Answers Brian Holian, Deputy Director Division of Reactor Projects U.S. NRC, Region I Indian Point Site I
I I
Fuel Route to ISFSI Overview Regulatory Framework ISFSI Licensing Pathways Security Considerations 11 Regulatory Framework Atomic Energy Act of 1954 Nuclear Waste Policy Act of 1982 10 CFR Part 72 Waste Confidence Decision Spent Fuel Project Office (SFPO)
Regulatory Process for Licensing of Dry Cask Storage Systems Larry Camper, Deputy Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards L
I NRC Mission Ensure adequate protection of public health and safety Promote the common defense and security Protect the environment ISFSI Licensing Pathways Specific License General License 2
Site-Specific Licensing Process 10 CFR Part 72, Subpart B Application with Safety Analysis Notice of Proposed Action and Environmental Assessment or At-Reactor or Away from Reactor Sites Report and Environmental Report Opportunity for Hearing Environmental Impact Statement I General Licensing Process Certificate of Compliance Usage
- 10 CFR Part 72, Subpart K
- Limited to Part 50 Reactor Licensees
- Requires Use of NRC-Certified Cask Designs General Licensing Process Certificate of Compliance Power Plant Selects, Evaluates, and Constructs the Dry Cask Storage System NRC Inspections General Licensing Process Part 50 License Holder Actions
- Evaluate and modify existing programs to support the ISFSI Quality Assurance Physical Security Emergency Planning
- Training Health Physics Procurement I
General Licensing Process Part 50 License Holders
-Inform NRC 90 days prior to first planned
- Register each cask with the NRC within
- Maintain individual cask records
- Maintain casks in accordance with loading 30 days Certificate of Compliance I
Security Considerations Compliance with 10 CFR Part 73 Issuance of Security Advisories Issuance of Security Orders Vulnerability Assessments NAS Study on Spent Fuel Storage 3
Dry Cask Storage Certificates of Compliance John D. Monninger, Chief Licensing Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards 2
Review and Approval Process Part 72, Sub art L - Approval of Spent Fuel Storage Casts
- Application to NRC
- Application available for public inspection
- Safety review
- Draft safety evaluation and draft Certificate of Compliance
- Notice of Rulemaking is published in Federal Register
- Review public comments
- Final safety evaluation and Issuance of Certificate of Compliance Technical Review Guidelines Standard Review Plan for Dry Cask Storage Systems (NUREG-1536)
Standard Review Plan for Spent Fuel Dry Storage Facilities (NUREG-1567)
Interim Staff Guidance Documents Hazards Considered Normal Operations Off-Normal Operations Design Basis Accidents Design Basis Natural Phenomena (e.g., Tornados, earthquakes, floods, lightning, tsunami, hurricanes)
Areas of Evaluation Principal Design Structural Program Thermal Radiation Shielding Protection Criticality Confinement 0 Operating Acceptance Tests Criteria and Maintenance Accident Analyses Conditions for Use Quality Assurance Procedures Decommissioning Conditions for Use Operating Procedures Acceptance Tests and Maintenance Quality Assurance Heavy Loads Design Features Pre-Operational Testing and Training Program 4
Approved Contents
--I.
Fuel Loading Patterns Fuel Type (PWR, BWR)
Cladding Type Enrichment Burnup Minimum Cooling Time Decay Heat Inspection Program for Dry Cask Storage Systems Dr. Ron Bellamy, Chief Projects Branch 6 Division of Reactor Projects U.S. NRC, Region I Proposed, Near Term Spent ISFSI Locations P u b I i c I y Ava i I ab I e I n f o r mat i o n E -
NRC's Web-site (www.nrc.qov)
- Electronic Reading Room (ADAMS web-Indian Point Proposed ISFSI (Docket ##
07200051)
Holtec HI-STORM 100 Certificate of Compliance (Docket # 07201 01 4) based access)
Operating S ent Fuel Storage (ISFSI~ Locations Indian Point's Dry Cask System Hi - Storm 100 (Certificate of Compliance 1014) f OPERATIONAL EXPERIENCE
- ARKPNSAS NUCLEAR (2003)
- COLUMBIA GWERATING STATION (2002)
- DRESDEN(=)
- EDWIN 1 HATCH 12003)
- F I l Z P A T R I C K ( ~ 1
- RVER BENO(ZQ041
- - TRWPNI2001)
SEOUOVAH (200&]
PLANNED
- BROWNS FERRY (2W5)
- HOPE CREEWSALEM 12WW
- OUAD CITIES 12005)
- DIPIBLOCPNYON 12006)
- PRIVATE FUEL STORAOE FAClUM 1200s) 5
3, IP 60856, 10CFR72.212(B) Evaluations
- QAProgram
- Radiation Protection Program
- Training Program I
IP 60857, 10CFR72.48 Evaluations NRC Inspection Program Component Fabrication ISFSI Construction Preoperational Testing Operations Security
~
I I
33 I
I ISFSI Construction I
- I IP 60852, ISFSI Fabricatlon by Outside Fabricators
- Construction of Systems, Structures, and Components in accordance with
- Safety Analysis Report
- Certificate of Compliance
- Containers Maintain Function
- Confinement
- Criticaiily
- Shielding
- Heat Removal
- Prevent damage to SNF containers during handling
- Health and safety of public is maintained Preoperational Testing Reviews IP 60854, Preoperational Testing of an ISFSI
- NRC observes and independently evaluates licensees capability I
I
- Test program and test procedures Component Fabrication IP 60851, Design Control of ISFSl Components
- Conditions of Certificate of Compliance are met
- Prior NRC approvals obtained
- No significant increase in occupational radiation exposure
- No significant unreviewed environmental impact I
I ISFSI Construction IP 60853, Onsite Fabricatlon of Components and Construction of an ISFSI
- Concrete storage containers built in accordance with
- Safely Analysis Report
- Safely Evaluation Report
- Certificate of Compliance
- Ouaiity Assurance program
- Subsoii compaction
- Rebar
- Concrete compressive strength
- Qualification construction workers
- Pad constructed to specifications I
I 6
Operations IP 60855, Operation of an ISFSI
- Loading Campaigns Frequency
- Long-term Operations and Surveillance Qualifications of Personnel Security/Safeguards
- Fire Protection Environmental Monitoring Maintenance I
31 1 Security I
IP 81001, Security and Safeguards at an ISFSI
- Security Pian
- Patrols
- Barrlers
- Detection Aids
- Access Control
- Local Law Enforcement Interface
- Compensatory Measures
- Contingencies
- Guard Training and Quaiificatlons
- Audits and Assessments 7