ML18295A073
| ML18295A073 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 10/24/2018 |
| From: | Bruce Watson Division of Decommissioning, Uranium Recovery and Waste Programs |
| To: | Budnitz R Diablo Canyon Independent Safety Committee |
| Watson B | |
| Shared Package | |
| ML18295A072 | List: |
| References | |
| Download: ML18295A073 (37) | |
Text
2 Safe Decommissioning Leads to License Terminations 0
2 4
6 8
10 12 Materials Sites Research Reactors Power Reactors Draft Guidance
Guiding Principles of Decommissioning Protection of plant &
workers Protection of the public Communications &
outreach with external stakeholders
Reactor Decommissioning The process of removing a reactor facility safely from the operating mode to a permanent shutdown condition and reducing the residual radioactivity to a level that permits the release of the property for unrestricted use and termination of the license.
BEFORE AFTER Maine Yankee
Initial Licensee Steps Certification of permanent cessation of operations Certification of permanent removal of fuel from reactor Submittal of the Post-Shutdown Decommissioning Activities Report (PSDAR)
Post-Shutdown Decommissioning Activities Report (PSDAR)
It contains:
Description of planned decommissioning activities
High-level schedule of planned decommissioning activities
Site-specific cost estimate for the decommissioning
Environmental impacts of decommissioning
PSDAR Review Process NRC notices receipt of the PSDAR in the Federal Register and requests public comments NRC schedules a public meeting to discuss PSDAR &
solicit public comments NRC considers public comments Plant owner may begin decommissioning work 90 days after NRC receives the PSDAR
DECON - Licensee immediately begins removal of equipment, structures, etc.,
and decontamination to a level that permits unrestricted release SAFSTOR - Plant is placed in a safe, stable condition and maintained in this state until it is subsequently decontaminated to levels that permit unrestricted release Decommissioning Options
How Long to Complete Decommissioning?
Under NRC regulations, the process must be completed within 60 years Site Restoration is determined by the owner and State Decommissioning typically takes 7-10 years.
Decommissioning Process - Phases Before Cleanup During Cleanup After Cleanup
Ready the plant for decommissioning Move spent nuclear fuel to dry cask storage Submit & update PSDAR
Removal of structures & components Soil remediation Radioactive waste shipments
NRC license termination Spent fuel management Site restoration
6 units in active decommissioning 15 units in SAFSTOR 12 plants have announced they will be permanently ceasing operations by 2025 New Business Models Power Reactors in Decommissioning
Oversight Program After Shutdown Oversight and monitoring conducted over the entire period of decommissioning process Oversight program is described in Inspection Manual Chapter (IMC) 2561 & 2690
Oversight Program After Shutdown Decommissioning inspection program includes both core and discretionary inspections Implementation depends on activities being planned or performed.
Post-Operation Transition Phase Actively Decommissioning - Fuel in Spent Fuel Pool Actively Decommissioning - No Fuel in Spent Fuel Pool SAFSTOR - Fuel in Spent Fuel Pool SAFSTOR - No Fuel in Spent Fuel Pool Final Surveys Under way
What Happens to the Spent Fuel?
Removed from spent fuel pool Stored on-site in dry cask storage systems Safety and security programs remain until fuel removed from site
Is the Spent Fuel Pool Safe?
Robust structures Designed to withstand severe natural events Regulated design features &
operational practices implemented to maintain fuel in safe condition
How Does Emergency Planning Change?
Emergency preparedness remains All hazards approach utilized vs. formal pre-planned off-site radiological response plans Decommissioning Rule Making to be completed by 2019 to make the transition more efficient
Emergency Plan Graded Approach Level 1 Permanent cessation of operations and all fuel in spent fuel pool Level 2 Spent fuel has sufficiently decayed (10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> adiabatic heatup time)
Level 3 All fuel is in dry cask storage Level 4 All fuel removed from site 20
Post-Shutdown Emergency Plan (PSEP)
PSEP may start after NRC dockets licensees certifications of certifications of permanent cessation of operations and permanent removal of all fuel from the reactor vessel.
PSEP is a transition period May only last 10 months (BWR) to 16 months (PWR)
Significant changes to plan not anticipated No changes to regulations for offsite emergency plan 21
Post-Shutdown Emergency Plan (PSEP) 10 CFR 50.200(a)
Proposed Rule provides for:
Reduced ERO staffing Revisions to EALs ETE updates no longer required Annual dissemination of information to the public future plant status Revised exercise schedule (drill cycle maintained) 22
Permanently Defueled Emergency Plan (PDEP) 10 CFR 50.200(b) and (c)
Proposed Rule provides for:
Reduced Emergency Response Organization staffing Classification and Notification timeliness commensurate to risk and accident timing Events classified as Notification of an Unusual Event or Alert No offsite (Radiological Emergency Plan) planning requirements o
No defined Emergency Planning Zones beyond the site boundary o
No demonstration of capability for prompt public alerting o
No pre-determined Protective Actions 23
Permanently Defueled Emergency Plan (PDEP)
Proposed Rule provides for:
Revisions to Emergency Action Levels (EALs)
Emergency response facilities (Technical Support Center, Operations Support Center, Emergency Operations Facility) may be combined Biennial exercise within 2 years of entering into decommissioning (drill cycle maintained)
No hostile action requirements (security EALs maintained) 24
Permanently Defueled Emergency Plan (PDEP) 10 CFR 50.47(f) Planning standards do not apply to offsite EP if Emergency Planning Zone does not extend beyond the site boundary.
10 CFR 50.54(s)(3) Clarifies how NRC will make findings and determinations of reasonable assurance when planning standards do not apply to offsite.
(s)(3)If the planning standards for radiological emergency preparedness apply to offsite radiological emergency response plans, the NRC will base its finding on a review of the FEMA findings and determinations as to whether State and local emergency plans are adequate and capable of being implemented, and on the NRC assessment as to whether the licensee's emergency plans are adequate and capable of being implemented.
10 CFR 50.54(t) EP program element review at 2 year intervals until all fuel in dry cask storage.
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Independent Spent Fuel Storage Installation (ISFSI) Only Emergency Plan (IOEP)
IOEP may start after all spent fuel is in dry cask storage IOEP utilizes established EP planning standards for ISFSIs contained in 10 CFR 72.32(a)
Part 50 and Part 52 licensees are granted a general Part 72 license Application for a specific Part 72 license would require NRC approval of emergency plan 26
Decommissioning Rulemaking by 2019 Emergency Plan Change Process Transition to Levels Changes within Levels Changes in Final Safety Analysis Report (FSAR)
Changes in Emergency Action Levels (EALs) Classifications and Scheme(s)
10 CFR 50.54(q)(7) Licensee may elect to follow and maintain a Level standard when conditions are met.
10 CFR 50.54(q)(8) Clarifies need for Reduction in Effectiveness (RIE)
Transition between levels is not an RIE if changes comply with standards.
Changes to e-plan are not RIEs if supported by Final Safety Analysis Report (FSAR) for Safety Systems and Components (SSCs) out of service.
Changes to EAL not RIE if physically unattainable.
Draft EP Regulatory Guide to accompany proposed rule DG-1346, Emergency Planning for Decommissioning Nuclear Power Reactors (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17311B018),
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Decommissioning EP Levels 28 Level 1 Post Shutdown Emergency Plan (PSEP) 10 months (BWR) 16 months (PWR)
Level 2 Permanently Defueled Emergency Plan (PDEP)
Level 3 ISFSI Only Emergency Plan (IOEP)
> 5 years Cessation of Power Operations and Defueled Power Operations Level 4 No Spent Fuel Onsite
How will plant security change?
Security controls remain in place Some key features include: intrusion detection and
- response, assessment of alarms, and off-site assistance, when necessary
Public Involvement on Decommissioning Public meeting to discuss the decommissioning process and the plants PSDAR NRC staff typically provide briefings at meetings of state/citizen decommissioning advisory panels An opportunity for a hearing Public meeting on License Termination Plan
2009 Rancho Seco
San Onofre 1, 2, 3
Humboldt Bay
Humboldt Bay - October 2018
NRC References
Links for NRC References IMC 2561: Decommissioning Power Reactor Inspection Program RG 1. 184: Decommissioning of Nuclear Power Reactors RG 1.185: Post Shutdown Decommissioning Activities Report NUREG 1628: Staff Responses to FAQs Concerning Decommissioning of Nuclear Power Reactors NRC Backgrounder: Decommissioning of Nuclear Power Plants NRC YouTube Video on Decommissioning Questions????
Bruce.Watson@nrc.gov or 301-415-6221