ML20128H678
| ML20128H678 | |
| Person / Time | |
|---|---|
| Issue date: | 03/26/1996 |
| From: | Haughney C, Travers W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20128H682 | List: |
| References | |
| ACRS-GENERAL, NACNUCLE, NUDOCS 9610100032 | |
| Download: ML20128H678 (80) | |
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JOINT ACRS/ACNW SUBCOMMITTEE MEETING O#-E MARCH 26,1996 WILLIAM D. TRAVERS, DIRECTOR
; -y ) CHARLES J. HAUGHNEY, DEPUTY DIRECTOR if, SPENT FUEL PROJECT OFFICE L. OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS !
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l Briefing Objectives I
- Introduce ACRS/ACXW Joint Subcommittee to Spent Fuel Project Office:
t> Responsibilities and Organization . r> Current and Anticipated Dry-Cask Storage Casework t> Dry Cask Storage Action Plan and Guidance Development
Creation of Spent Fuel Project Office
- Increasing Workload -MPC AND MRS
> Increasing Casework for Commercial Sites
- Common Elements in Transportation and Storage Reviews
- Combination of Transportation and Storage Reviews (e.g., Dual and Multipurpose Casks)
- Increasing Congressional and Public Interest
- Spent Fuel Project Office Formed Within NMSS in May 1995, Fully-Staffed Complement of 53 FTE
/* "'*%,
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umrEo STATES NUCLEAR REGULATORY Commission Spent Fuel Project Office
- Office of Nuclear Material Safety and Safeguards William D. Travers, Director i Charles J, Haughney, Deputy Director M .
Earl Easton, Section Leader Transportation & Safety Section Ross ChappeII,Section Leader John P. Jankovich, Section Leader Package Certification Section Inspection Section Fritz C. Sturz,Section Leader Spent FuelTechnical Review Section c J. Spent Fuel L; censing Sections Secdon M per i
Spent Fuel Project Office Responsibilities
- ISFSI Licensing, Inspection Program Development and Project Management
- Storage and/or Transport Cask Certification for Spent Fuel; Transport Package Certification for Other Radioactive .
Materials Packages
- Review / licensing of Centralized Storage Facilities
- Multi-Purpose Canister Review, Burnup Credit Review
- Implement Regulatory Program for Safe Transportation of Licensed Radioactive Materials; DOT /IAEA Interface
- Quality Assurance Program Reviews and Inspections
SNF Storage & Transport Systems
- 1 Dual Purpose (Storage / Transport) Cask NAC-STC (26 PWR) -
- 8 Transport Casks for LWR SNF IF-300 (7 PWR,17-18 BWR) TN-8, TN-8L (3 PWR)
TN-9 (7 BWR) NAC-LWT (1 PWR,2 BWR) NLI-1/2 (1 PWR,2 BWR) TN-BRP (44 BWR) NLI-10/24 (10 PWR,24 BWR) TN-REG (20 PWR)
- 12 Dry Storage Systems NUHOMS-24P (24 PWR) STANDARDIZED NUHOMS VSC-24 (24 PWR) [NUHOMS-24P (24 PWR), -
CASTOR V/21 (21 PWR) NUHOMS-52B (52 BWR)] CASTOR X-28 (28 PWR) MC-10 (24 PWR) NAC-I28 S/T (28 PWR) NAC-C28 S/T (56 PWR assembhes TN-24 (24 PWR) , consolidated into 28 canisters) NUHOMS-7P (7 PWR) Modular Vault Dry Storage (83 PWR/150 BWR) TN-40 (40 PWR)
- - - _ - - - - - - - - - - - _ - - - --- n
General License (10 CFR Part 72 Subpart K)
- Issued to power reactor licensees for storage of spent fuel in :SRC-approved casks (10 CFR 72.210)
- Section 133 of the :SWPA required :SRC to develop such a rule
- Final Rule - published July 18,1990, (55 FR 29181) effective August 17,1990
*New cask designs added by rulemaking
Site Specific License, (10 CFR Part 72)
- Pre Licensing Consultation
- Application
- Notice of Receipt .
- Opportunity for Hearing
- Hearing if Requested t
- Direct Review of an Application -
l l i l
4 Existing Sites of Spent Fuel Dry Cask Storage Systems (ISFSI's) .
..........................._---.-----------------------------------------~~--------7 Ft. Saint Vrain Point Beach Prairie Island
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Current SFPO Major Casework '
- Standardized :SUHOMS: 1 Amendment Oyster Creek, Susquehanna, Fitzpatrick
- Vectra MP-187 Rancho Seco Holtec HI-STAR 100/HI-STAR 100-STORM Dresden (HI-STAR 100)
- Sierra Nuclear VSC-24: 2 Amendments Arkansas Nuclear One
- Sierra Nuclear TRANSTOR Trojan
- Transnuclear TS~-32 North Anna, Surry amendment
- GA-4/9 Cask Review
- Burnup Credit Topical Report Review
i Potential Near-Term, New Sites for Spent Fuel Dry Cask Storage Systems s 1 . #, :m . . .
. . . .-e ..
WNP2 Mescalero FitzPatrick Trojan ' Dresden
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SFPO Anticipated Cask Casework
- DOE TMI-2 Fuel Storage at INEL
- DOE Topical: Cask to Cask Transfer System
*NAC-International L niversal Cask
- Multipurpose Canister (DOE / Westinghouse?)
- Prairie Island Off-Site ISFSI #2 Advance Container Systems Inc. Dual Purpose Cask
- L .S. Fuel and Security
Centralized Interim Storage Facility Initiatives
- HR 1020/S 1271
> Centralized Storage Facility at Area 25 of Nevada Test Site > Phased Licensing, Second Phase could be Licensed for 100 Years ; > NRC Must Issue License Within 16 Months of Application > January 1998 Acceptance of Fuel > S 1271 Gives Budgetary Priority to Storage Over Disposal
- Mescalero Apache Tribe Initiative '
> New Mexico > Joint Initiative With Over 30 Utilities > Pre-Application Meeting Held With Staff, 8/95 > Late 1996 Application Planned
Dry Storage Issues O
- OverallInconsistent Performance 1
- Utility Oversight Essential
- Fabricators / Vendors: QA Programs and Principles Not Observed
- 72.48 Evaluations Poorly Documented
- XRC Expectations not Clearly Communicated
- Public Confidence Jeopardized
NRC Initiatives for Improved Internal and Industry Communication
- Develop Joint:SRR/SMSS Dry Cask Storage Action Plan
- Review Parts 71 and 72 for Clarity, Revise and/or Issue Guidance as Needed
- Coordinate with Industry: ;
& Regulatory Information Conference session
> Dry Cask Storage Workshop - May 1995
> Pre-fabrication Meeting With Utilities
- Detailed Reviews of Loading and Unloading Procedures
Guidance Development
- Issued 5 Inspection Procedures (2/96)
> Design Control
> Off Site Fabrication
> On Site Construction
> Pre-Operational Testing
> Operations
- Inspection Manual Chapter 2690 I
- Draft Standard Review Plan for SXF Storage Systems (3/96)
Plans for additional SRPs
> ISFSI Site Licensing
> Transportation Cask Review i
Dry Cask Storage Action Plan Subjects
- Near-Term Technical Issues
- Long-Term Technical Issues
- Communications t> Internal to NRC t> External to NRC
- Processes
l Dry Cask Storage Action Plan Near-Term TechnicalIssues
- Heavy Load and Crane Evaluations
- Trunnion Design and Preoperational Testing Values i
- Hydrostatic Testing Requirements
> Seismic Evaluation Requirements l
Dry Cask Storage Action Plan ' l Long-Term TechnicalIssues
- Cask Weeping
- Cask Loading and Unloading Procedures
- Off-Loading Capability
> Failed Fuel Storage
- Safeguards
l Dry Cask Storage Action Plan Communications -Internal to NRC i
- Coordination Among XMSS, NRR And Regional Offices
- Training XMSS, NRR And Regional Staff on Cask Design Bases
- Training Regional Staff on Dry Cask Inspection Issues
- Periodic Meetings Among Affected NRC Staff
Dry Cask Storage Action Plan Communications -External i
- Issue Generic Communications for ISFSI Related Issues
- Hold Periodic Workshops on Dry Cask Storage Issues With Industry
- Meet With XEI to Discuss Recent Issues And Industry Initiatives
- Support XRR Responses to Public Inquiries
{
NRC Expectations
- Utilities t> Early Involvement t> Frequent Communications with NRC and Public
& Aggressive QA Oversight
- Vendors t> Ensure that applications are high quality
& Establish & implement a strong QA program & Actively review design changes & Communicate often with utilities & fabricators
- Fabricators t> Adhere strictly to QA program t> Document all deviations thoroughly
& Justify all changes in detail & Communicate often with vendor and utility
,f. .. ..,,, ,
(g*') United States Nuclear Regulatory Commission - t Overview of NRC's Decommissioning Program and Responsibilities i Michael Weber Division of Waste Management March 1996 i
l PROGRAM RESPONSIBILITIES NRR
- Licensing power reactor decommissioning prior to permanent removal of fuel f
- Licensing non-power reactor decommissioning NMSS
- Licensing power reactor decommissioning after fuel removal l
- Licensing materials and fuel facility
- decommissioning
- Site Decommissioning Management Plan
.. . _ _ - .. - _ - =_ . _ _ . _ - _ .
PROGRAM RESPONSIBILITIES (Continued) Regions
- e Inspection and enforcement of licensee decommissionmg e
Licensing materials facility decommissioning RES e Rulemaking to establish and update decommissionmg requirements , r
DEFINITION t Decommission means to remove (as a facility) safely from service and reduce residual radioactivity to a level that permits release of ' the property for unrestricted use and termination of license. t i
MATERIALS DECOMMISSIONING ; e NRC terminates about 300 licenses each year e Most license terminations are routine with limited potential for residual radioactivity t e Less than 10% are non-routine terminations ; i
/ Fuel cycle facilities !
/ SDMP sites e NRC is also reviewing formerly terminated licenses
l l DECOMMISSIONING PROCESS , Cessation of Operations ! 4 , Site Characterization Plan 4 - Site Characterization 4 . t Site Characterization Report , 4 Decommissioning Plan and Environmental Report j 4 NRC Environmental Review Process 4 i License Amendment 4 Decommissioning j 4 i Final and Confirmatory Survey j 4 License Termination and Site Release ; f
SITE DECOMMISSIONING MANAGEMENT PLAN
- Program Management Plan
/ Objectives
/ Responsibilities
/ Resources
- Contaminated Sites
/ Listing /Delisting Criteria
/ Site Descriptions
/ Status
- Policy Issues s
1 f u---___- _ _ _ _ _ _ - - _ _ _ - - _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - - _ _ - _ _ _ _ - - - _ - - - -
POLICY ISSUES Problem Solution Poor recordkeeping Decommissioning recordkeeping rule - 1993 Formerly terminated licenses review - 1991 to present Manual Chapter on Decommissioning (draft under review) No schedule constraints SDMP Action Plan - 1992 License conditions and orders Decommissioning timeliness rule - 1994 No residual radioactivity standards SDMP Action Plan - 1992 Enhanced Participatory Rulemaking - 1993 to present (Proposed rule in August 1994; final rule in 1996) Inadequate fmancial assurance General decommissioning requirements - 1988 License renewals and conditions Financial assurance clarification rule - 1994 Orders and enforcement i Inadequate procedures for Survey procedures (NUREG/CR-5849) - 1992 termination and surveys Standard Review Plan - 1993 Inspection Procedures - 1995 Decommissioning Manual Chapter - in process Multi-Agency Radiological Site Investigation Manual - in process
l I REMAINING CHALLENGES t e Codifying radiological criteria for license termination "how clean ! is clear," e Upgrading financial assurances for decommissioning ; l e Streamlining review process and confirmatory surveys ; , + e Completing review of formerly terminated licenses (1950s to , present) e Maturing and implementing the program
/ Program guidance - licensing and inspection
/ Licensee guidance - modeling, surveys, restricted use
/ Program oversight - ongoing and periodic reviews i
t i
l 1 {~ > < ) United States
\, ,,,,,
) Nuclear Regulatory Commission i
DECOMMISSIONING TODAY
- PRESENTATION TO THE ACRS MARCH 26,1996 SEYMOUR H. WEISS PROJECT DIRECTOR NON-POWER REACTORS AND DECOMMISSIONING PROJECT DIRECTORATE l DIVISION OF REACTOR PROGRAM MANAGEMENT OFFICE OF NUCLEAR REACTOR REGULATION i
r 4 WHAT 13 DECOMMISSIONING? Decommissioning means to remove (as a facility) safely from service and reduce residual radioactivity to a level that permits release of the property for unrestricted or restricted use and termination of the license. Does not include care and disposal of spent fuel
- Does not include non-radiological demolition (Example: restoration to " green field" conditions)
- Covered separately by 10 CFR 50.54 (bb) which requires submittal of spent fuel management and fundmg program.
_ - - - _ - - - - _ - - - - - - - - - -_ L
DECOMMISSIONING ALTERNATIVES
- e Under DECON (immediate dismantlement), portions of the facility containing radioactive contamiaants are removed or decontaminated to a level that permits release for unrestricted use. (See Reg. Guide 1.86 for current guidance) e Under SAFSTOR, or " delayed DECON," radiation levels fall for up to 60 years; the facility is then dismantled.
e Under ENTOMB, radioactive contaminants are maintained and monitored until the radioactivity , decays to a level permitting unrestricted release of the property. (Currently allowed only for a 60 year period).
- Described in Generic Environmental Impact Statement on Decommissioning; NUREG-0586.
+
COMPLETED & CURRENT DECOMMISSIONING PROJECTS e 64 research and test reactor licenses terminated e 11 research and test reactors now being dismantled or have license amended for Possession-Only e 17 power reactors in decommissioning process 2 power reactors completed Pathfinder & Shoreham 1 power reactor now being dismantled Fort St. Vrain
COMPLETED & CURRENT DECOMMISSIONING PROJECTS (Continued) 9 power reactors with approved SAFSTOR decommissioning plans CVTR, Dresden, Fermi 1, GE VBWR, Humboldt Bay 3, La Crosse, Peach Bottom 1, Rancho Seco, & Indian Point 1; 4 power reactor decommissioning plans have been received, Big Rock Point, San Onofre 1, Trojan, Yankee Rowe & Saxton ! TYPICAL CURRENT REGULATORY PROCESS FOR PREMATURE DECOMMISSIONING I l
- Continued compliance with license and regulations is required after shutdown l
- Licensee submits license amendments / relief requests to NRC
- Possession-only license amendment Reliefs / exemptions granted may include:
Containment leak testing Licensed operators Offsite emergency preparedness reduction Property damage liability insurance reduction
- Decommissioning plan approved by Order -
RULEMAKING ACTIVITIES i f 1 i
- Radiological Release Criteria for Decommissioning Facilities
- Decommissioning Rule
- Revise Spent Fuel Pool Fire Sequence Affected Regulations and indemnity Levels for Permanently Shut Down Reactors
- Physical Protection for Storage of Spent Fuel
- Decommissioning Cost and Funding Evaluations i i
i
.:i,;' : , ll l !! ! ! Ii ; ? !
- I tI '
g - n g - i . n n i o i n n - s i s l a _. m p m n - E C e o c e i t o c - N d i D e - A u p D g r s - I f o n - U w i G e t n d - - n e n L a t a 8 A e n - _- C I b C o w e - N l i v e l H i d - C W n r E a r T t o 6 a f . 8 m e r c - 1 o n F s a - G da l d R i u e r t ait g i s v dm n f f - e ab t u t a R SS S e e e
PLANT DECOMMISSIONING STATUS 1 lNDIAN POINT UNIT 1 e January 31,1996, the order approving SAFSTOR decommissioning plan was issued. Spent fuel will remain onsite until federal repository available. License extended until 2006. I i HUMBOLDT BAY POWER PLANT UNIT 3 l e Shut down in July 1976; July 1988-NRC approved SAFSTOR Decommissioning Plan & extended license until 2015. e Activities continue in accordance with approved Plan. Spent fuel will remain onsite in spent fuel pool until l federal repository is available. Considering early component removal program. Y _g_
DRESDEN UNIT 1 i
- Shut down in October 1978. SAFSTOR Decommissioning Plan & license extension approved m :
September 1993. e Activities continue in accordance with approved Plan. Comed plans to go to dry cask storage. . RANCHO SECO e Shut down in June 1989. SAFSTOR Decommissioning i Plan approved in March 1995. e Conducting activities in accordance with approved plan. e SMUD internal review considering DECON decommissioning alternative.
- Part 72 (specific license) ISFSI pad is completed and
- horizontal storage modules are being delivered. Part 71 (transportation) license application undergoing NRC l
- review for multipurpose (storage / transport) cask.
i Licensee could be r'eady to offload fuel to ISFSI by l October 1996. l
YANKEE ROWE e Shut down in October 1991. SAFSTOR Decommissioning Plan approved February 1995. Appeals Court decision (July 1995) granted hearing opportunity. o On March 1,1996, after a prehearing conference, Atomic Safety and Licensing Board issued an order stating its finding regarding the joint petition of Citizens Awareness Network and New England Coalition on Nuclear Pollution to intervene on the Yankee decommissioning plan. Although the ASLB determined the petitioners had standing, the ASLB did not find any of the five contentions to be admissible. Subsequent Commission order prevents staff re-approval of Plan until appeal process completed.
- Yankee Atomic applied for a (10 CFR 71) license to enable shipment of the reactor vessel. The vessel will not be shipped before summer 1996.
- Yankee intends to pursue dry cask storage of its spent fuel. -
_ _.= _ I
THREE MILE ISLAND UNIT 2
- Accident occurred in March 1979; Defueling completed April 1990 e License plans for Post-Defueling Monitored Storage i (PDMS) and Possession-Only License approved by NRC m 1993.
o Conducting activities in accordance with approved PDMS technical specifications. SAN ONOFRE, UNIT 1 1 e Shut down November 1992. e Conducting activities in accordance with approved permanently defueled technical specifications. Proposed , decommissioning plan awaiting NRC review. i e Licensee considering ISFSI, but has not submitted Part ! 72 license request.
--------_ ---_ ___ i
TROJAN
- Shut down November 1991
- November 1,1995, licensee completed the large component removal project. i e Commission issued order preventing further dismantlement until final decommissioning plan approved.
e No requests for hearing received after December 22, l 1995, Federal Register notice on Environmental Assessment and Safety Evaluation for decommissioning l plan.
- Combined NRC/ State of Oregon public meeting held February 13,1996, to discuss the results of NRC and State decommissioning plan review.
- No requests for hearing received by State of Oregon after its public notice. Hearing regarding Stata approval of decommissioning plan held on March 7,1996. State approval granted.
i TROJAN (Continued) e Licensee is considering removing the pressure vessel with ! reactor vessel internals intact and shipping by barge to low-level waste repository at Hanford in early 1998. e Licensee selected Sierra Nuclear as vendor for dry cask ; storage commencing in 1998. i BIG ROCK POINT ; e May 31, 2000, is expiration date of current license. e Proposed SAFSTOR Decommissioning Plan undergoing : NRC review. Licensee requested NRC deferral of review ' until after revised decommissioning regulations issued.
- p. ~ ~.,,
- s
- 1. j Decommissioning of Nuclear Power Reactors - Mnal Rule
- Pmposed rule issued July 20,1995 (60 FR 37374)
- Incorporated SRMS of January 14 and June 30,1993
- Incorporated draft policy statement on use of decommissioning trustfunds before decommissioning plan appmval (59 FR 5216; FEB. 319%)
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%.... l Proposed Rule Requirements
- Eliminated needfor decommissioning plan approval t
- Before decommissioning aedvides could begin, licensees would submit:
(1) Certs)icadons ofpermanent cessation of operations and (2) Permanent removal offuelfrom reactor vessel
- Prohibited operation of reactor and extended certain Part 50 requirements to decommissioning activities l
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(Proposed rule condaned)
- Imposed 90 day waidagperiod before major decommissioning (depned in rule) could occur - included public information meeting in vicinity of site
- Allowed use of Q 50.59 to dismantle facility with addition of 4 criteria
- Written notspcation required for any activities inconsistent with PSDAR or a sigmpcant schedule change fmm PSDAR
- FSAR updating required ,
V 3 -o O
i g># 88 G% y 4 i 3 s i
\,...../ .
(Proposed rule condaned) License terminaden process -
- Submittal oflicense terminadon plan and supplement to ER
- Public information meeting held '
- License amendment process including opportunity for hearing under subpart L (or G sffuel onsite) 4
~
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(Proposed rule coneinned) : Mnancial assurance -
- Continued to require preliminary cost estimate at 5 years prior to license expiration i
- Allowed staged use of decommissioning funds (based on draft policy statement)
- Permitted use of 3% of generic amount prior to cessation of operations, 20% - 90 days after PSDAR submittal, and remainder aper site-specsyc cost estimate received 5 .
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(Proposed mie conninned) Grandfathering-
- Permitted licensee with approved plan option of continuing as in current rule or i t
switching to new process - License extension -
- Clanflied that license does not terminate until Commission decision i
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Public comments
- 34 comment letters received
- Comments addressed all aspects ofproposed rule plus court's decision on Yankee Rowe. No comments on non-power reactor amendments i
e Commenters (24) generally in fawr of the proposed rule consisted ofpower reactor licensees, reactor industry gmups and consultants, government agencies, and an r Agreement State 7 4 , e t
gkF AI G(/g O c (Comments contbened) .
- Commenters (10) genemlly opposed consisted of citizen' gmups, individuals, and an Agreement State
- Many commenters in favor of the rule wanted less restrictions than offered by the proposed rule
- Many commenters opposed preferred the stattss quo - several favored greater restrictions than the current rule requires 8
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Maal Rule Schedule
- Staff analysis of comments completed, draftpnal rule undergoing staff review t
- Final Rule due to Commission in earty April,19%
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REACTOR DECOMMISSIONING RULE Presentation to Joint ACRS/ACNW Subcommittee March 26,1996 ; I Cheryl A. Trottier ' Section Leader : Radiation Protection and Health Efects Branch i Division of Regulatory Applications Offee of Nuclear Regulatory Research i i i
I I Decommissioning of Nuclear Power Reactors - Final Rule
- Proposed rule issued July 20,1995 (60 FR 37374)
- Incorporated SRMS ofJanuary 14 and June 30,1993 Incorporated draft policy statement on use of decommissioning trustfunds before .l decommissioning plan approval (59 FR 5216; FEB. 31994) l i
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Proposed Rule Requirements
- Eliminated needfor decommissioning plan approval
- Before decommissioning activities could begin, licensees would submit:
(1) Certifications ofpermanent cessation of operations and (2) Permanent removal offuelfrom reactor vessel . Prohibited operation of reactor and extended certain Part 50 requirements to decommissioning activities 3
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(Proposed rule continued) Imposed 90 day waitingperiod before major decommissioning (defincd in rule) could , occur - included public information meeting in vicinity of site Allowed use of % 50.59 to dismantlefacility with addition of 4 criteria
- Written notification required for any activities inconsistent with PSDAR or a sigmjicant schedule changefrom PSDAR
- FSAR updating required 4
D CEct, [ 0, L 9 g,'ov / (Proposed rule continued) License termination process -
- Submittal oflicense termination plan and supplement to ER
- Public information meeting held
- License amendment process including opportunity for hearing under subpart L (or G iffuel onsite) 5
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Financial assurance - I
- Continued to require preliminary cost estimate at 5 years prior to license expiration
- Allowed staged use of decommissioning funds (based on draft policy statement) ,
- Permitted use of 3% of generic amount prior to cessation of operations, 20% - 90 days after PSDAR submittal, and remainder after site-specific cost estimate ;
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(l'toposed rule continued) Grandfathering-Permitted licensee with approved plan option of continuing as in current nde or switching to new process License extension - ; Clanfied that license does not terminate until Commission decision i i t 7 i
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Public comments
- 34 comment letters received Comments addressed all aspects ofproposed rule plus court's decision on Yankee Rowe. No comments on non-power reactor amendments
- Commenters (24) generally infavor of the proposed rule consisted ofpower reactor licensees, reactor industry groups and consultants, government agencies, and an Agreement State 8
- - - - - - - - - - - - - - - - -- ---- J
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(Comments continued) Commenters (10) generally opposed consisted of citizen' groups, individuals, and an Agreement State i Many commenters in favor of the rule wanted less restrictions than offered by the proposed rule Many commenters opposed preferred the status quo - several favored greater ' restrictions than the current rule requires r 9 . f l
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Specipe comments
- Eliminate PSDAR requirements - more stringent than for operating reactor
- Eliminate PSDAR update because Q 50.59 already requires annual reporting .
- Require lessfrequent FSAR updates (e.g., every 36 months) -
Ninety day time periodprior to allowance of major decommissioning activities Not a health and safety concern - activities covered under % 50.59 and licensing basis i Costly to licensees because it would delay dismantling 10 . i
paccoq, w%* *+.., (Specific commments continued) Section 50.59 modifications For-
- Existing b 50.59 criteria are adequate Requirements in k 50.59(e) are redundant and more stringent than for operating reactors
- Decommissioning activities are routine and similar to permitted operational activities Against-
- After thefact reviews of activities provides insufficient regulatory protection The presence of an on-site NRC inspector during activaties is essential 11
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Environmental impact considerations - initialphase of decommissioning For-
- Strongly supported elimination of ER and EA
- Nofurther EI address necessary because already covered in previous EISs ,l
- Requested a categorical exclusion 4
Against-
- Should require an EA or EIS ;
i
- A generic EIS is no substitutefor specipc EA Elimination of EA (and decommissioning plan approval) gives utilities too much responsibility and undermines citizens due process 12 i
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(Specufic comments continued) Public participation For-e Questioned needfor expanded public participation Additional guidance on purpose of the public meeting is necessary 'l Adequate mechanisms should be developedfor addressing public concerns Against-
- Public participatory role is inadequate
- Retain POLA and decommissioning plan approval
- SSABs should be established early in the decommissioning process 13
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(Specipe comments continued) l Use of decommissioning trustfund For-
- Want greaterflexibility in costs that can be included (e.g., operational LLWdisposal ;
costs) . Percentages of costs permitted (% 50.75) are too low - raise percentages or permit ' higher estimates , {, 14
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(Specyic comments continued) Modipcations to specific technical requirements For -
- Requested additional elimination or modification of requirements
- Requested additional modifications especially forfuel in ISFSI or offsite 15 i
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k / y** ** * , l (Specipe comments continued) Termination oflicense requirements For-
- Several commenters believed approval oflicense termination should not require an amendment or hearing opportunity -public comment ana existing regulations are ,
adequate, especially iffuel offsite
- Ifstandardsfor radionuclide release are clear, terminating the license can be easily demonstrated without prior approval Against -
- supported license termination requirements, but viewed them as too late in pms 16
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(Specipe comments continued) Elimination of POLA Against -
- Eliminates hearing opportunities (Subpart G) and State consultation (% 50.91(b)) *
- Delays needfor an amendment until termination stage, which is too late
- Logic ispoor because non-power reactors, which are less hazardous to decommission than power reactors, still will permit POLAs and require an approved decommissioning plan .
i 17
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l } United States
%. ,,) Nuclear Regulatory Commission l
l
- RULEMAKING ISSUES
! RADIOLOGICAL CRITERIA FOR LICENSE TERMINATION March 26,19% b John E. Glenn Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, D.C. 20555 . t i t D I o l D
(g) Background , v Published proposed rule for comment - 8/94 v Workshop on SSABs - 12/94
- NUREG/CR-6307 - 6/95 -
/ Public comment period closed - 1/95
! - NUREG/CR-6353 - 10/95 , v Extended rule schedule - 8/95 V Workshop on implementation of rule - 9/95
~
De relopment of Regulatory Guidance on Decorranissioning
. .. ..s Overview of Public
($) Comments v 101 different commenters government agencies
- licensees .
public groups
- industry groups .
- Native American organizations
- individuals v General reactions varied
- agreement / disagreement on provisions, e.g., restricted use
- disagreement for differing reasons on provisions, e.g.,15 mrem E . . _, . .. , _ _. __,_
, ,. . 9, (g) 20.1402(b) 15 mrem /y
/ Agree with 15 v Disagree with 15 -
- too high - return to background' preferred
- too low,- 25-100 mrem /y with ALARA preferred v Issues on both sides -
- health impacts
- costs vs impacts
- ability to measure such low doses
- relationship with background
- effects on disposal capacity n ,ch> m is g g g y jig g th,pther standards
]
($) 20.1402(c) ALARA v Require ALARA analysis to assess doses < 15 mrem /y v Don't require ALARA analysis < 15 mrem /y l
- large costs ,
- small reduction in risk v Allow ALARA analysis to move standard > 15 mrem /y v Don't permit ALARA > 15 mrem /y t
ei....t . .....,,e ,,e n,.,u. tat,wv Gesh1ance on Decommissioning i
,-~s 20.1402(a) Restricted
($) Release , 1
< Agree
- allows consideration of realistic land uses, protects public health and permits flexibility
- rely on institutional controls - don't assume eventual failure
- should be allowed if ALARA or if under continuous owner control as in further industrial use v Disagree
- institutional controls uncertain, can't be enforced indefinitely or can become ineffective
- no responsible regulatory oversight L v Suggest possible Federal ownership or legislative solutions 5 n - , - ,e,e ,. , ,c _ . _ , ,
l
, 20.1405(d) i (g)100 mrem /y Cap v Toolow :
- should not assume all institutional controls will fail ,
~
allow 500 mrem /y cap , v Too high
- institutional controls are uncertain
- use 15-75 mrem /y t
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20.1403 ~ ($) General Provisions :
/ EPA Drinking water standard i oppose ;
prefer single dose based, all pathway standard j
- support
- consistent with EPA rule v Calculation to 1000 years post decommissioning
- use > 1000 years for long lived radionuclides
- use < 1000 years to be consistent with 10 CFR 40 and 61
- 200-500 years t)evelopment of Regulatory Guidance on Decommissioning
($) 20.1407 SSABs . v Differing views
- - Support for provision
- SSAB not always the best solution, other options should be ok
- extend use of SSABs to unrestricted use sites v Provide more detail ,
responsibilities I membership, size, qualifications, government role independence from licensee ! - administrative and financial support i
- meetings .. .. ........J.liG.9RESSAgCRC use of SSAB recommendations ,}}