ML13267A143: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
(One intermediate revision by the same user not shown)
Line 15: Line 15:


=Text=
=Text=
{{#Wiki_filter:Aust 2 0REG&Reco DcmisinngBac 0 THE HUMBOLDT BAY LICENSE TERMINATION PLAN August 20, 2013 John B. Hickman Project Manager Reactor Decommissioning Branch Division of Waste Management and Environmental Protection Office of Federal and State Materials and Environmental Management Programs oft REG;&4,>0-Bruce Watson, Nuclear Regulatory Commission"NRC REGULATORY PROCESS-John Hickman, Nuclear Regulatory Commission" LICENSE TERMINATION PLAN-Pacific Gas and Electric Company* NRC INSPECTION AND OVERSIGHT PROGRAM-Blair Spitzberg, Nuclear Regulatory Commission
{{#Wiki_filter:Aust 2   0REG&
* PUBLIC COMMENTS* CLOSING REMARKS 0;" 141,..DECOMMISSIONING PROCESS* Facility Permanently Ceases Operations
0 THE HUMBOLDT BAY Reco  DcmisinngBac LICENSE TERMINATION PLAN August 20, 2013 John B. Hickman Project Manager Reactor Decommissioning Branch Division of Waste Management and Environmental Protection Office of Federal and State Materials and Environmental Management Programs
-June 1983* Operating License No Longer Permits Operation-Amended July 1988* Decommissioning Plan-Planned Decommissioning Activities (SAFSTOR -30 years)-Schedule for the Planned Activities
 
-Site-specific Cost Estimate" License Termination Plan* Final Status Surveys" License Terminated tphf REG(j, Li, 0 RESTRICTIONS The Licensee Is Prohibited at Any Time from Performing Any Decommissioning Activities That:-Would Not Allow the Release of the Site for Unrestricted Use; or-Result in Significant Environmental.
oft REG;&4,>
Impacts Not Previously Considered; or-Result in There No Longer Being Reasonable Assurance That Adequate Funds Will Be Available.  
0
"I 0 NRC FOCUS DURING DECOMMISSIONING
      -       Bruce Watson, Nuclear Regulatory Commission "NRC REGULATORY PROCESS
* The Safe Removal of Radiological Hazards-The Removal Of The Facility From Service-Reduction Of Radioactive Materials To A Level That Allows Site Release-Detailed Final Radiological Survey
      -       John Hickman, Nuclear Regulatory Commission
:W,,;LICENSE TERMINATION PLAN The Plan Will Describe:-Site Characterization
" LICENSE TERMINATION PLAN
-Identification of Remaining Dismantlement Activities
      -       Pacific Gas and Electric Company
-Plans for Site Remediation
* NRC INSPECTION AND OVERSIGHT PROGRAM
-Plans for the Final Radiation Survey-Description of the End Use of the Site If Restrictions Are Imposed-Updated Site-specific Cost Estimate of Remaining Costs-Any New Information to Supplement the Environmental Report REG~jl3"It*NRC REVIEW OF THE LTP* Acceptance Review* Technical Review* Request Additional Information if Necessary* Public Meeting / Opportunity for a Hearing* NRC approves LTP by License Amendment" NRC Performs In-process Inspections NRC REVIEW OF THE LTP" Licensee Submits Final Status Survey Report" NRC Reviews and Approves FSSRs* NRC Will Perform Confirmatory Surveys* The License Is Terminated If the License Termination Plan Was Followed and the Site Meets the Release Criteria 00cNRC CONTACT INFORMATION
      -       Blair Spitzberg, Nuclear Regulatory Commission
* John Hickman NRC Project Manager for Rancho Seco Office of Federal and State Materials and Environmental Management Programs U.S. Nuclear Regulatory Commission Washington DC 20555 301-415-3017 john.hickman@nrc.gov" Blair Spitzberg, Chief Repository and Spent Fuel Safety Branch Division of Nuclear Materials Safety U.S. NRC Region IV 1600 E. Lamar Blvd.Arlington, TX 76011 817-200-1191 blair.spitzberg@nrc.gov" NRC Documents are available at: http://www.nrc.gov/reading-rm.html I ýr 14 9 Ali,'RJ 3.TF w %M4 P I C."' : ý ý Az ý 1 -EH;roperty 4 l Site Infrastructure Improvements Installation of planning trailers 2008 Construction of new access road Sep. 2009 New Access Control Apr. 2010 Portal monitor and truck scale Sep. 2010 5 HBPP?: A Unique Decommissioning PLAN AT EL H~ 2'-O" The reactor vessel is located inside the drywell, below grade within the Refueling Building 6 igniticant Radiologica[
* PUBLIC COMMENTS
Activities Spent Fuel Pool Racks Feb 2010 Control Rod Blades Aug 2010 Reactor Head Main Steam Line Apr 2010 Lower core shroud removed March 2013 UZI% ingR.1 u r i W a vvlw o r k Ar e 8 Uni 3Casso Rmoal , ý T" Above-Ground Demo.ition Slurry Wa.l InstaLlation and Caisson Removal_ýit ~TnzcksEquipannt Removing Components  
* CLOSING REMARKS
-41116 Backfill and Restoration For illustrative purposes.
 
Image not to scale.
;"   141,..DECOMMISSIONING 0
9 M 5-%,,~~ f __ 'l,%nrvaa e LTP Process Approximate Timeline Genera Site Information
PROCESS
* Chapter 1 provides information about the site and lays out the licensing notification and approval requirements relating to any deviations from or changes to the LTP.* Addresses historical information about the site as well as summarizing the content of the remaining seven chapters U i S) 2Et Cactrztion
* Facility Permanently Ceases Operations
* Provides information regarding A..y the radiological state of the site using input from the historical site assessment, site spill records and continuing characterization data.* Characterization will continue to take place and the LTP will be updated as necessary as new data becomes available.
  - June 1983
LTP Chapter 3 12 F Remaining Decommision"ing Activities" Describes the methods and sequence of remaining decommissioning work." Done at a high level, in other words, major activities are identified and an estimated completion date is provided so the NRC can identify any inspections and technical resources that will be needed." The chapter also includes site dose estimates, waste volumes and radiological effluents for the entire decommissioning.  
* Operating License No Longer Permits Operation
--e 4~*~4b 13 L h a pt*Describes the means and methods to accomplish the remaining work scope of remediation to meet the NRC's release criteria.Include a detailed description of the techniques that will be employed to remove or remediate surface and subsurface soils, groundwater, and surface water and sediments.
  - Amended July 1988
SLTP Ch.ape 5 o,14 i* ..~ ~ ~ ~ ~ ~ ~ ~ ..c.. ..' -.: ". ." .... : .........  
* Decommissioning Plan
.....* The LTP describes the final radiation' survey plan for demonstrating that the plant and site will meet the release limits.* The final status survey is the radiation survey performed after an area has been fully characterized, remediation has been completed, and the area is ready to be released.* The purpose of the final status survey is to demonstrate that the area conforms to the radiological criteria for license termination.
  - Planned Decommissioning Activities (SAFSTOR - 30 years)
LT Chptr 15 Com ace W Radiological Criteria* Most technical of the chapters* Describes the process implemented to develop the site dose models and Derived Concentration Guideline Levels (DCGLs), including input parameter justification and sensitivity analyses.* DCGLs are radionuclide-specific values determined by a software program that correlate to the site release criteria.
  - Schedule for the Planned Activities
P Chapter 7 16 F nancial Status.... ..:.. .. .. .- .. .. ... ...... Describes the financing of the...........decommissioning project, with very detailed cost estimates which .usually includes some proprietary information related to contractual information.
  - Site-specific Cost Estimate
" License Termination Plan
* Final Status Surveys
" License Terminated
 
tphf REG(j, Li,         0 RESTRICTIONS The Licensee Is Prohibited at Any Time from Performing Any Decommissioning Activities That:
    -   Would Not Allow the Release of the Site for Unrestricted Use; or
    -     Result in Significant Environmental. Impacts Not Previously Considered; or
    -     Result in There No Longer Being Reasonable Assurance That Adequate Funds Will Be Available.
 
"I   0 NRC FOCUS DURING DECOMMISSIONING
* The Safe Removal of Radiological Hazards
    - The Removal Of The Facility From Service
    - Reduction Of Radioactive Materials To A Level That Allows Site Release
    - Detailed Final Radiological Survey
:W,,;LICENSE TERMINATION PLAN The Plan Will Describe:
  - Site Characterization
  - Identification of Remaining Dismantlement Activities
  - Plans for Site Remediation
  - Plans for the Final Radiation Survey
  - Description of the End Use of the Site If Restrictions Are Imposed
  - Updated Site-specific Cost Estimate of Remaining Costs
  - Any New Information to Supplement the Environmental Report
 
REG~jl3 "It*
NRC REVIEW OF THE LTP
* Acceptance Review
* Technical Review
* Request Additional Information if Necessary
* Public Meeting / Opportunity for a Hearing
* NRC approves LTP by License Amendment
" NRC Performs In-process Inspections
 
NRC REVIEW OF THE LTP
" Licensee Submits Final Status Survey Report
" NRC Reviews and Approves FSSRs
* NRC Will Perform Confirmatory Surveys
* The License Is Terminated If the License Termination Plan Was Followed and the Site Meets the Release Criteria
* 00 cNRC CONTACT INFORMATION
* John Hickman NRC Project Manager for Rancho Seco Office of Federal and State Materials and Environmental Management Programs U.S. Nuclear Regulatory Commission Washington DC 20555 301-415-3017 john.hickman@nrc.gov
" Blair Spitzberg, Chief Repository and Spent Fuel Safety Branch Division of Nuclear Materials Safety U.S. NRC Region IV 1600 E. Lamar Blvd.
Arlington, TX 76011 817-200-1191 blair.spitzberg@nrc.gov
" NRC Documents are available at:
http://www.nrc.gov/reading-rm.html
 
Iýr 14 9
: Ali,
    'RJ
 
.TF w %M4 3
P IC."'Az:ýýEH; 1- roperty
 
4 l     Site Infrastructure Improvements Installationof planning trailers2008 Construction of new access road Sep. 2009 New Access ControlApr. 2010       Portalmonitor and truck scale Sep. 2010
 
5 HBPP?: A Unique Decommissioning PLAN AT EL H~ 2'-O" The reactor vessel is located inside the drywell, below grade within the Refueling Building
 
6 igniticant Radiologica[                     Activities Spent Fuel Pool Racks Feb 2010           ControlRod Blades Aug 2010 Reactor Head Main Steam Line Apr 2010 Lower core shroud removed March 2013
 
%   ingR.1               UZI u r   i W a vvlw o r k     Ar e
 
8 Uni 3Casso                               Rmoal
                                                                                                ý
                                                                                                ,T" Above-Ground Demo.ition           Slurry Wa.l InstaLlation and Caisson Removal_ý Backfill and Restoration it     ~TnzcksEquipannt Removing Components -
41116 For illustrativepurposes. Image not to scale.
 
9 M 5-%
      ,,~~ 'l,%nrvaaf      __              e LTP Process Approximate Timeline
 
Genera Site Information
* Chapter 1 provides information about the site and lays out the licensing notification and approval requirements relating to any deviations from or changes to the LTP.
* Addresses historical information about the site as well as summarizing the content of the remaining seven chapters
 
S) UCactrztion 2Et                               i
* Provides information regarding       A..y the radiological state of the site using input from the historical site assessment, site spill records and continuing characterization data.
* Characterization will continue to take place and the LTP will be updated as necessary as new data becomes available.
 
LTP Chapter 3                                       12 FRemaining Decommision"ing Activities
" Describes the methods and sequence of remaining decommissioning work.
" Done at a high level, in other words, major activities are identified and an estimated completion date is provided so the NRC can identify any inspections and technical resources that will be needed.
" The chapter also includes site dose estimates, waste volumes and radiological effluents for the entire decommissioning.
 
L      h a pt--e 4~*~4b                         13
*Describes the means and methods to accomplish the remaining work scope of remediation to meet the NRC's release criteria.
Include a detailed description of the techniques that will be employed to remove or remediate surface and subsurface soils, groundwater, and surface water and sediments.
 
SLTP Ch.ape 5     o,14 i* ~ ~~ ~ ~ ~ ~ ~: .............
                                            ../.;.*:i
                                            '-.: ".                   .c..
* The LTP describes the final radiation' survey plan for demonstrating that the plant and site will meet the release limits.
* The final status survey is the radiation survey performed after an area has been fully characterized, remediation has been completed, and the area is ready to be released.
* The purpose of the final status survey is to demonstrate that the area conforms to the radiological criteria for license termination.
 
15 LT   Chptr ace W Com      Radiological Criteria
* Most technical of the chapters
* Describes the process implemented to develop the site dose models and Derived Concentration Guideline Levels (DCGLs), including input parameter justification and sensitivity analyses.
* DCGLs are radionuclide-specific values determined by a software program that correlate to the site release criteria.
 
P Chapter 7                                                 16 F nancial Status Describes the financing of the                     *    . .*
decommissioning project, with very detailed cost estimates which           .
usually includes some proprietary information related to contractual information.
* Funding status for the operation of the temporary spent fuel storage is not included in this chapter, however it is required in the annual financial assurance document sent to the NRC.
* Funding status for the operation of the temporary spent fuel storage is not included in this chapter, however it is required in the annual financial assurance document sent to the NRC.
i17 Suplmettoth E~onena Repoft.Provides an update to the 1984 environmental report.The goal of this chapter is to demonstrate that the project poses no environmental impacts that would exceed those described in the NRC's Generic Environmental Impact Statement.
 
i17 Suplmettoth   E~onena           Repoft.
Provides an update to the 1984 environmental report.
The goal of this chapter is to demonstrate that the project poses no environmental impacts that would exceed those described in the NRC's Generic Environmental Impact Statement.
* Describes any new information or significant environmental changes associated with the site-specific termination activities from the time the dismantlement and decommissioning activities began until the license isterminated.
* Describes any new information or significant environmental changes associated with the site-specific termination activities from the time the dismantlement and decommissioning activities began until the license isterminated.
LIV-1.42 I'l UJI 1:111.1 F rbs6nt 6'',d, by L an.pj -e An..........v4 R Inpcto Progra fo Deomisonn Reatos Pu lic Meeting on Humboldt Bay Nuclear Power Plant License Termination Process Eureka, California August 20, 2013 U.S. NUCLEAR REGULATORY COMMISSION HEADQUARTERS, REGIONAL STATE AGREEMENT, AND LIAISON OFFICER.. As of March 2012 CONTACTS BY REGION Region IV Region III Region I VTNMW Q--MA CT RI CT ovndi-- E Noi-Region 111 ha jurisdia overmakias-nldd-sue and Ringion IV has-ý mw nd relaied issues i kiluinmu mi Region II (see No*)R Agremewt Staes (37)r-1 FRC Stas(13)NOTW: This nap ooaesponds to Oe dmision of US. Nuclea Requi~ory Commisision Regiania Oft"s bY radildlim ivwniis Icensg and inspection auspouuh11iy As a resul t old* Oc*ober~l)3 restrucbumt regioni roles aid respoambilliesi, fuel cycle inspebm ln fim ~u*um al Oe Regions mi we omidamled a
 
* AeRe=o 11 .9k. ihn Aan. G&.and al radaioinnuemneiails lieuukig and mopectimfunclions i Region lime hardened 6 Region L Hoer. Region 11 retas its madornarmukilities.  
LIV-1.42 I'l           UJI 1:111.1 F rbs6nt 6'',d, by L an.
~U.S.NRC-US.NRC How NRC Ensures Safety United States Nuclear Regulatory Commission Protecting People and the Environment" Establish and ensure adherence to requirements contained in:-Regulations
pj     -e An v4
-Safety standards-License" License conditions" Technical Specifications" Perform licensing reviews and safety evaluations" Inspection and enforcement  
 
#-i'US.NRC Ongoing Inspection United States Nuclear Regulat Protecting People and tie Environment Activities at Humboldt Bay" Decommissioning inspections
R       Inpcto                   Progra           fo Deomisonn                               Reatos Pu lic Meeting on Humboldt Bay Nuclear Power Plant License Termination Process Eureka, California August 20, 2013
-Generally scheduled during periods of higher risk activities
 
-Conduct independent radiological measurements to confirm licensee survey methodologies
U.S. NUCLEAR REGULATORY COMMISSION HEADQUARTERS, REGIONAL STATE AGREEMENT, AND LIAISON OFFICER CONTACTS BY REGION
                        ..                                     As of March 2012 Region IV Region III                             Region I VTNMW Q--MA RI CT ovndi CT
                                                                                                                                      --   E Noi ha jurisdia
                                                                            -Region 111                                     mi overmakias-nldd
                                                                              -sueand Ringion IVhas
                                                                              -ý     mw nd                                 Region II relaied issuesi kiluinmu                         (see No*)
Agremewt R       Staes (37)       NOTW: This nap ooaesponds to Oe dmision of US. Nuclea Requi~ory Commisision Regiania Oft"s bY radildlim ivwniis Icensg and inspection auspouuh11iy As a resul told* Oc*ober~l)3 restrucbumt   regioni roles aid r-1 FRC Stas(13)              respoambilliesi, fuel cycle inspebm lnfim ~u*um al Oe Regions miwe omidamled a
* AeRe=o 11.9k. ihn Aan. G&.
and al radaioinnuemneiails lieuukig and mopectimfunclions i Region lime hardened 6 Region L Hoer.Region 11 retas its madornarmukilities.
 
-US.NRC
~U.S.NRC                                   How NRC Ensures Safety United States Nuclear Regulatory Commission ProtectingPeople and the Environment
  "     Establish and ensure adherence to requirements contained in:
          - Regulations
          - Safety standards
          - License
                  " License conditions
                  " Technical Specifications
  "     Perform licensing reviews and safety evaluations
  " Inspection and enforcement
 
  #-i'US.NRC United States Nuclear Regulat Ongoing Inspection ProtectingPeople and tie Environment Activities at Humboldt Bay
  "     Decommissioning inspections
          - Generally scheduled during periods of higher risk activities
          -     Conduct independent radiological measurements to confirm licensee survey methodologies
* ISFSI inspections
* ISFSI inspections
-ISFSI is authorized by a separate specific NRC Part 72 license.-ISFSI will operate to store the irradiated fuel after the Part 50 reactor license is terminated
          - ISFSI is authorized by a separate specific NRC Part 72 license.
* Physical Security inspections  
          -     ISFSI will operate to store the irradiated fuel after the Part 50 reactor license is terminated
*$'US.NRC Objectives of the NRC Inspection Leg~a"Program Protecting People and the Environment" Objectively verify safe conduct of licensee activities
* Physical Security inspections
* Verify adequacy of licensee controls* Ensure safety problems and violations are promptly identified and corrected and effective actions are taken to prevent recurrence" Examine trends in licensee safety performance  
 
'.US.NRC Examples of Core Inspection UnitdSauleRegutoOrfo==S),o Procedures for Decommissioning Protecting People and the Environment" Organization, Management and Cost Controls* Safety Reviews, Design Changes and Modifications
*$'US.NRC                               Objectives of the NRC Inspection Leg~a"Program ProtectingPeople and the Environment
* Self Assessments, Audits and Corrective Actions" Safety of spent fuel* Occupational Radiation Exposure" Inspection of Final Surveys* Radwaste Treatment, Effluent & Environmental Monitoring
  "   Objectively verify safe conduct of licensee activities
* Transportation of Radioactive Material* Maintenance and Surveillance" Physical Security* Contingency response procedures S$US.NRC Inspection Planning and United States Nuclear Regulatory Commission Protecting People and the Environment Commu nications 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-Inspection may be announced or unannounced
* Verify adequacy of licensee controls
-Inspection plan approved by Region IV management  
* Ensure safety problems and violations are promptly identified and corrected and effective actions are taken to prevent recurrence
-Identifies scope, IPs, follow-up issues, participating personnel-Exit Meetings -Any significant changes in findings from those communicated in the final exit will require re-exiting with licensee management
  " Examine trends in licensee safety performance
* Post inspection debrief of NRC management and staff (Generally the week of return to office )" Coordinate any enforcement  
 
-NRC enforcement policy http:i/pbadu pws.nrc.aov/docs/M L0934/M L093480037.pdf" Issue Inspection Report-30 day goal for normal inspection reports (post exit)-45 day goal for team inspections (post exit)* Determine need for any follow-up 1fU.S.NRC I hJm I .So1 .Neoaor C Post Inspection Activities Protecting People and the Environment" Prompt NRC management debrief" Determination of any significant findings* Need for enforcement?" Issue inspection report To locate reports -go to ADAMS web page (http://www.nrc.gov/readinq-rm/adams.html), use advanced search feature with docket number 050-00133* Track and follow up on safety issues  
    '.US.NRC UnitdSauleRegutoOrfo==S),o Examples of Core Inspection Procedures for Decommissioning ProtectingPeople and the Environment
*US.NRC United States Nuclear Regulatory Commission Humboldt Bay Decommissioning Safety Record Protecting People and the Environment" How many inspections?
  "   Organization, Management and Cost Controls
-4 in 2011-6 in 2012 -Included extensive independent radiological surveys conducted by NRC contractor laboratory Oak Ridge Institute for Science and Education (ORISE)-4 in 2013 (3 conducted, 1 underway)* Violations, significant enforcement?
* Safety Reviews, Design Changes and Modifications
-There has been one Severity Level III violation in the last two years involving control of security-related information with two examples.-Otherwise a good recent enforcement history of licensee's decommissioning work U .S.NRC Region IV Contacts United States Nuclear Regulatory Commission Protecting People and the Environment" D. Blair Spitzberg, Ph.D., Chief, Fuels Safety and Decommissioning Branch-Blair.SpitzberqC&nrc.qov
* Self Assessments, Audits and Corrective Actions
-(817) 200-1191* Send correspondence to: Tony Vegel, Director, Division of Nuclear Materials Safety U.S. Nuclear Regulatory Commission, Region IV 1600 East Lamar Blvd.Arlington, TX 76011-4511
  "   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
 
S$US.NRC United States Nuclear Regulatory Commission   Inspection Planning and ProtectingPeopleand the Environment                   Commu nications 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
          -   Inspection may be announced or unannounced
          -   Inspection plan approved by Region IV management - Identifies scope, IPs, follow-up issues, participating personnel
          - Exit Meetings - Any significant changes in findings from those communicated in the final exit will require re-exiting with licensee management
* Post inspection debrief of NRC management and staff (Generally the week of return to office )
  "     Coordinate any enforcement - NRC enforcement policy http:i/pbadu pws.nrc.aov/docs/M L0934/M L093480037.pdf
  "     Issue Inspection Report
          - 30 day goal for normal inspection reports (post exit)
          - 45 day goal for team inspections (post exit)
* Determine need for any follow-up
 
1fU.S.NRC IhJm I       .So1.Neoaor       C   Post Inspection Activities ProtectingPeople and the Environment
  "   Prompt NRC management debrief
  " Determination of any significant findings
* Need for enforcement?
  " Issue inspection report To locate reports - go to ADAMS web page (http://www.nrc.gov/readinq-rm/adams.html), use advanced search feature with docket number 050-00133
* Track and follow up on safety issues
 
*US.NRC United States Nuclear Regulatory Commission Humboldt Bay Decommissioning Safety ProtectingPeople and the Environment Record
  "     How many inspections?
          -   4 in 2011
          -   6 in 2012 - Included extensive independent radiological surveys conducted by NRC contractor laboratory Oak Ridge Institute for Science and Education (ORISE)
          -   4 in 2013 (3 conducted, 1 underway)
* Violations, significant enforcement?
          -   There has been one Severity Level III violation in the last two years involving control of security-related information with two examples.
          -   Otherwise a good recent enforcement history of licensee's decommissioning work
 
U .S.NRC United States Nuclear Regulatory Commission Region IVContacts ProtectingPeople and the Environment
  "     D. Blair Spitzberg, Ph.D., Chief, Fuels Safety and Decommissioning Branch
          - Blair.SpitzberqC&nrc.qov
          - (817) 200-1191
* Send correspondence to:
Tony Vegel, Director, Division of Nuclear Materials Safety U.S. Nuclear Regulatory Commission, Region IV 1600 East Lamar Blvd.
Arlington, TX 76011-4511
* Region IV main switchboard (817) 860-8100}}
* Region IV main switchboard (817) 860-8100}}

Latest revision as of 02:34, 6 February 2020

Presentation Slides from August 20, 2013 Public Meeting on the Humboldt Bay Power Plant License Termination Plan
ML13267A143
Person / Time
Site: Humboldt Bay
Issue date: 08/20/2013
From: John Hickman
NRC/FSME/DWMEP
To:
References
Download: ML13267A143 (37)
v • d • e


Text

Aust 2 0REG&

0 THE HUMBOLDT BAY Reco DcmisinngBac LICENSE TERMINATION PLAN August 20, 2013 John B. Hickman Project Manager Reactor Decommissioning Branch Division of Waste Management and Environmental Protection Office of Federal and State Materials and Environmental Management Programs

oft REG;&4,>

0

- Bruce Watson, Nuclear Regulatory Commission "NRC REGULATORY PROCESS

- John Hickman, Nuclear Regulatory Commission

" LICENSE TERMINATION PLAN

- Pacific Gas and Electric Company

  • NRC INSPECTION AND OVERSIGHT PROGRAM

- Blair Spitzberg, Nuclear Regulatory Commission

  • PUBLIC COMMENTS
  • CLOSING REMARKS
" 141,..DECOMMISSIONING 0

PROCESS

  • Facility Permanently Ceases Operations

- June 1983

  • Operating License No Longer Permits Operation

- Amended July 1988

  • Decommissioning Plan

- Planned Decommissioning Activities (SAFSTOR - 30 years)

- Schedule for the Planned Activities

- Site-specific Cost Estimate

" License Termination Plan

  • Final Status Surveys

" License Terminated

tphf REG(j, Li, 0 RESTRICTIONS The Licensee Is Prohibited at Any Time from Performing Any Decommissioning Activities That:

- Would Not Allow the Release of the Site for Unrestricted Use; or

- Result in Significant Environmental. Impacts Not Previously Considered; or

- Result in There No Longer Being Reasonable Assurance That Adequate Funds Will Be Available.

"I 0 NRC FOCUS DURING DECOMMISSIONING

  • The Safe Removal of Radiological Hazards

- The Removal Of The Facility From Service

- Reduction Of Radioactive Materials To A Level That Allows Site Release

- Detailed Final Radiological Survey

W,,;LICENSE TERMINATION PLAN The Plan Will Describe:

- Site Characterization

- Identification of Remaining Dismantlement Activities

- Plans for Site Remediation

- Plans for the Final Radiation Survey

- Description of the End Use of the Site If Restrictions Are Imposed

- Updated Site-specific Cost Estimate of Remaining Costs

- Any New Information to Supplement the Environmental Report

REG~jl3 "It*

NRC REVIEW OF THE LTP

  • Technical Review
  • Request Additional Information if Necessary
  • Public Meeting / Opportunity for a Hearing
  • NRC approves LTP by License Amendment

" NRC Performs In-process Inspections

NRC REVIEW OF THE LTP

" Licensee Submits Final Status Survey Report

" NRC Reviews and Approves FSSRs

  • NRC Will Perform Confirmatory Surveys
  • The License Is Terminated If the License Termination Plan Was Followed and the Site Meets the Release Criteria
  • 00 cNRC CONTACT INFORMATION
  • John Hickman NRC Project Manager for Rancho Seco Office of Federal and State Materials and Environmental Management Programs U.S. Nuclear Regulatory Commission Washington DC 20555 301-415-3017 john.hickman@nrc.gov

" Blair Spitzberg, Chief Repository and Spent Fuel Safety Branch Division of Nuclear Materials Safety U.S. NRC Region IV 1600 E. Lamar Blvd.

Arlington, TX 76011 817-200-1191 blair.spitzberg@nrc.gov

" NRC Documents are available at:

http://www.nrc.gov/reading-rm.html

Iýr 14 9

Ali,

'RJ

.TF w %M4 3

P IC."'Az:ýýEH; 1- roperty

4 l Site Infrastructure Improvements Installationof planning trailers2008 Construction of new access road Sep. 2009 New Access ControlApr. 2010 Portalmonitor and truck scale Sep. 2010

5 HBPP?: A Unique Decommissioning PLAN AT EL H~ 2'-O" The reactor vessel is located inside the drywell, below grade within the Refueling Building

6 igniticant Radiologica[ Activities Spent Fuel Pool Racks Feb 2010 ControlRod Blades Aug 2010 Reactor Head Main Steam Line Apr 2010 Lower core shroud removed March 2013

% ingR.1 UZI u r i W a vvlw o r k Ar e

8 Uni 3Casso Rmoal

ý

,T" Above-Ground Demo.ition Slurry Wa.l InstaLlation and Caisson Removal_ý Backfill and Restoration it ~TnzcksEquipannt Removing Components -

41116 For illustrativepurposes. Image not to scale.

9 M 5-%

,,~~ 'l,%nrvaaf __ e LTP Process Approximate Timeline

Genera Site Information

  • Chapter 1 provides information about the site and lays out the licensing notification and approval requirements relating to any deviations from or changes to the LTP.
  • Addresses historical information about the site as well as summarizing the content of the remaining seven chapters

S) UCactrztion 2Et i

  • Provides information regarding A..y the radiological state of the site using input from the historical site assessment, site spill records and continuing characterization data.
  • Characterization will continue to take place and the LTP will be updated as necessary as new data becomes available.

LTP Chapter 3 12 FRemaining Decommision"ing Activities

" Describes the methods and sequence of remaining decommissioning work.

" Done at a high level, in other words, major activities are identified and an estimated completion date is provided so the NRC can identify any inspections and technical resources that will be needed.

" The chapter also includes site dose estimates, waste volumes and radiological effluents for the entire decommissioning.

L h a pt--e 4~*~4b 13

  • Describes the means and methods to accomplish the remaining work scope of remediation to meet the NRC's release criteria.

Include a detailed description of the techniques that will be employed to remove or remediate surface and subsurface soils, groundwater, and surface water and sediments.

SLTP Ch.ape 5 o,14 i* ~ ~~ ~ ~ ~ ~ ~: .............

../.;.*:i

'-.: ". .c..

  • The LTP describes the final radiation' survey plan for demonstrating that the plant and site will meet the release limits.
  • The final status survey is the radiation survey performed after an area has been fully characterized, remediation has been completed, and the area is ready to be released.
  • The purpose of the final status survey is to demonstrate that the area conforms to the radiological criteria for license termination.

15 LT Chptr ace W Com Radiological Criteria

  • Most technical of the chapters
  • Describes the process implemented to develop the site dose models and Derived Concentration Guideline Levels (DCGLs), including input parameter justification and sensitivity analyses.
  • DCGLs are radionuclide-specific values determined by a software program that correlate to the site release criteria.

P Chapter 7 16 F nancial Status Describes the financing of the * . .*

decommissioning project, with very detailed cost estimates which .

usually includes some proprietary information related to contractual information.

  • Funding status for the operation of the temporary spent fuel storage is not included in this chapter, however it is required in the annual financial assurance document sent to the NRC.

i17 Suplmettoth E~onena Repoft.

Provides an update to the 1984 environmental report.

The goal of this chapter is to demonstrate that the project poses no environmental impacts that would exceed those described in the NRC's Generic Environmental Impact Statement.

  • Describes any new information or significant environmental changes associated with the site-specific termination activities from the time the dismantlement and decommissioning activities began until the license isterminated.

LIV-1.42 I'l UJI 1:111.1 F rbs6nt 6,d, by L an.

pj -e An v4

R Inpcto Progra fo Deomisonn Reatos Pu lic Meeting on Humboldt Bay Nuclear Power Plant License Termination Process Eureka, California August 20, 2013

U.S. NUCLEAR REGULATORY COMMISSION HEADQUARTERS, REGIONAL STATE AGREEMENT, AND LIAISON OFFICER CONTACTS BY REGION

.. As of March 2012 Region IV Region III Region I VTNMW Q--MA RI CT ovndi CT

-- E Noi ha jurisdia

-Region 111 mi overmakias-nldd

-sueand Ringion IVhas

-ý mw nd Region II relaied issuesi kiluinmu (see No*)

Agremewt R Staes (37) NOTW: This nap ooaesponds to Oe dmision of US. Nuclea Requi~ory Commisision Regiania Oft"s bY radildlim ivwniis Icensg and inspection auspouuh11iy As a resul told* Oc*ober~l)3 restrucbumt regioni roles aid r-1 FRC Stas(13) respoambilliesi, fuel cycle inspebm lnfim ~u*um al Oe Regions miwe omidamled a

  • AeRe=o 11.9k. ihn Aan. G&.

and al radaioinnuemneiails lieuukig and mopectimfunclions i Region lime hardened 6 Region L Hoer.Region 11 retas its madornarmukilities.

-US.NRC

~U.S.NRC How NRC Ensures Safety United States Nuclear Regulatory Commission ProtectingPeople and the Environment

" Establish and ensure adherence to requirements contained in:

- Regulations

- Safety standards

- License

" License conditions

" Technical Specifications

" Perform licensing reviews and safety evaluations

" Inspection and enforcement

  1. -i'US.NRC United States Nuclear Regulat Ongoing Inspection ProtectingPeople and tie Environment Activities at Humboldt Bay

" Decommissioning inspections

- Generally scheduled during periods of higher risk activities

- Conduct independent radiological measurements to confirm licensee survey methodologies

- ISFSI is authorized by a separate specific NRC Part 72 license.

- ISFSI will operate to store the irradiated fuel after the Part 50 reactor license is terminated

  • Physical Security inspections
  • $'US.NRC Objectives of the NRC Inspection Leg~a"Program ProtectingPeople and the Environment

" Objectively verify safe conduct of licensee activities

  • Verify adequacy of licensee controls
  • Ensure safety problems and violations are promptly identified and corrected and effective actions are taken to prevent recurrence

" Examine trends in licensee safety performance

'.US.NRC UnitdSauleRegutoOrfo==S),o Examples of Core Inspection Procedures for Decommissioning ProtectingPeople and the Environment

" 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

S$US.NRC United States Nuclear Regulatory Commission Inspection Planning and ProtectingPeopleand the Environment Commu nications 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

- Inspection may be announced or unannounced

- Inspection plan approved by Region IV management - Identifies scope, IPs, follow-up issues, participating personnel

- Exit Meetings - Any significant changes in findings from those communicated in the final exit will require re-exiting with licensee management

  • Post inspection debrief of NRC management and staff (Generally the week of return to office )

" Coordinate any enforcement - NRC enforcement policy http:i/pbadu pws.nrc.aov/docs/M L0934/M L093480037.pdf

" Issue Inspection Report

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

- 45 day goal for team inspections (post exit)

  • Determine need for any follow-up

1fU.S.NRC IhJm I .So1.Neoaor C Post Inspection Activities ProtectingPeople and the Environment

" Prompt NRC management debrief

" Determination of any significant findings

  • Need for enforcement?

" Issue inspection report To locate reports - go to ADAMS web page (http://www.nrc.gov/readinq-rm/adams.html), use advanced search feature with docket number 050-00133

  • Track and follow up on safety issues
  • US.NRC United States Nuclear Regulatory Commission Humboldt Bay Decommissioning Safety ProtectingPeople and the Environment Record

" How many inspections?

- 4 in 2011

- 6 in 2012 - Included extensive independent radiological surveys conducted by NRC contractor laboratory Oak Ridge Institute for Science and Education (ORISE)

- 4 in 2013 (3 conducted, 1 underway)

  • Violations, significant enforcement?

- There has been one Severity Level III violation in the last two years involving control of security-related information with two examples.

- Otherwise a good recent enforcement history of licensee's decommissioning work

U .S.NRC United States Nuclear Regulatory Commission Region IVContacts ProtectingPeople and the Environment

" D. Blair Spitzberg, Ph.D., Chief, Fuels Safety and Decommissioning Branch

- Blair.SpitzberqC&nrc.qov

- (817) 200-1191

  • Send correspondence to:

Tony Vegel, Director, Division of Nuclear Materials Safety U.S. Nuclear Regulatory Commission, Region IV 1600 East Lamar Blvd.

Arlington, TX 76011-4511

  • Region IV main switchboard (817) 860-8100
Retrieved from "https://kanterella.com/w/index.php?title=ML13267A143&oldid=2455282"