ML20205P153
| ML20205P153 | |
| Person / Time | |
|---|---|
| Issue date: | 12/31/1998 |
| From: | Pittiglio C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| References | |
| NUREG-1700, NUREG-1700-DRFT, NUREG-1700-DRFT-FC, NUDOCS 9904200045 | |
| Download: ML20205P153 (20) | |
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'77 Standard Review Plan for EvaluatingJpelear Power RefcMrfoicense Termination Plans Draft Report for Comment M
d (gv U.S. Nuclear Regulatory Commission
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Office of Nuclear Material Safety and Safeguards i
Washington, DC 20555-0001 9 g 42 g 981231 1700 R PDR J
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NUREG-1700 Standard Review Plan for Evaluating Nuclear Power Reactor License Termination Plans Draft Report for Comment Manuscript Completed: December 1998 Date Published: December 1998 Prepared by C.L. Pittiglio Division of Waste Management OfUce of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 pt* *"%,
l
COMMENTS ON DRAFT REPORT Any interested party may submit comments on this report for consideration by the NRC staff.
Comments may be accompanied by additional relevant information or supporting data. Please specify the report number draft NUREG-1700, in your comments, and send them by June 15,1999 to:
Chief, Rules Review and Directives Branch U.S. Nuclear Regulatory Commission Mail Stop T6-D59 Washington, DC 20555-0001 You may also provide comments at the NRC Web site, http://www.nrc. gov. See the link under " Technical Reports in the NUREG Series" on the " Reference Library" page.
Instmetions for sending comments electronically are included with the document, NUREG-1700, Draft, at the web site.
For any questions about the material in this report, please contact:
Larry Pittiglio Mail Stop: TWFN 7-F27 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Phone: 301-415-6702 E-mail: CLP
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ABSTRACT The standard review plan (SRP) guides NRC the purpose of the SRP to make the staffin performing safety reviews oflicense information about regulatory matters widely termination plans (LTPs). Although interested available in order that interested members of parties can use it for conducting their own the public and the nuclear industry gain a licensing reviews or developing an LTP, the better understanding of the staff's review principal purpose of the SRP is to ensure the process. Each SRP presents the acceptance quality and uniformity of NRC staff reviews criteria for all areas of review for license and to present a well-defined base from which termination. The SRP identifies the matters to to evaluate the requirements for terminating be reviewed, the basis for the review, and the the license of a nuclear power plant. It is also conclusions that are sought.
i i
iii Draft NUREG-1700
r' 1
l CONTENTS Page A. I NTRODU CTI ON.........................................................,,,,
1 l
' B.
LTP STANDARD REVIEW PLAN AND ACCEPTANCE CRITERIA..................
2 1.
Ge ne ral Information........................................................
2 2.
Site Characterization........................................................
3 3.
Identification of Remaining Site Dismantlement Activities........................
4 4.
Reme diati on Plans..........................................................
4 5.
Final Radiation Smvey Plan.................................................
4 6.
Compliance With the Radiological Criteria for License Termination...............
6 7.
Update of the Site-Specific Decommissioning Costs..............................
9 i
8.
Supplement to the Environmental Report...........................
10 C. EVALUATI ON FINDINGS......................................................
10 D. IMPLEM ENTATION............................................................
11 E.
REFE RENCES.................................................................
11 l
I I
J l
l l
l l
t i
i l
1 l
i v
Draft NUREG-1700 I
u-
A. INTRODUCTION licensee to make certain changes that do not result in an unreviewed safety question or changes to the technical specifications, and the On July 29,1996, the Commission published changes must meet the requirements of 10 amendments to its regulations in 10 CFR CFR 50.82(a)(6).
Parts 2,50, and 51 (61 FR 39278, Ref.1),
prescribing specific criteria for On July 21,1997, the Comr tission amended its decommissioning nuclear power reactors, regulations in 10 CFR Parts 20,30,40,50,51, effective August 28,1996. This rule, by 70, and 71 (62 FR 39058, Ref. 3), prescribing eliminating, revising, or extending operating Specific radiological criteria for license reactor requirements commensurate with the termination. Draft Regulatory Guide importance to safety, specifies requirements DG-4006," Demonstrating Compliance With for reactors that are permanently shut down the Radiological Criteria for License and have no fuel in the reactor vessel. Such Termination" (Ref. 4), provides additional reactors present a significantly reduced risk to guidance on how to demonstrate compliance the public, with the unrestricted release, restricted release, and alternate criteria for license Decommissioning activities for power reactors termination in accordance with Subpart E of may be divided into three phases: (1) initial 10 CFR Part 20.
activities; (2) major decommissioning and storage activities; t.nd (3) license termination Under the new regulations in the LTP, a activities. Draft Regulatory Guide DG-1067, 11 ensee may propose either
" Decommissioning of Nuclear Power release of the facility and site for Reactors" (Ref. 2), is being developed to unrestricted use or describe methods and procedures that are acceptable to the U.S. Nuclear Regulatory release of the facility and site under Commission (NRC) staff for implementing the restricted-use conditions.
rules that relate to the initial activities and the major phases of decommissioning.
For the most part, the LTP will contain a final site characterization, a dose assessment, For Phase 3,10 CFR 50.82(a)(9) specifies that identification of the remaining remediation an application for license termination must be activities and supporting plan, and a final accompanied or preceded by a license survey plan. The LTP must be subnutted as a termination plan (LTP), which is subject to supplement to the licensee's final safety NRC review and approval. According to 10 analysis report (FSAR) or as an equivalent CFR 50.82(a)(9)(i), the licensee must submit document. A h,eensee might submit the LTP an LTP at least two years before termination
license amendment. A public meeting must be Guidance on the content of the PSDAR can be held near the site; any hearing held in relation f und in draft Regulatory Guide DG-1071, to the LTP would fall under either Subpart G
" Standard Format and Content Guide for j
or Subpart L of 10 CFR Part 2. If the fuel has Post-Shutdown Decommissioning Activities been permanently removed from the Part 50 Report"(Ref. 5).
license to an authorized facility, a hearing on Currently, the Office of Nuclear Material the proposed LTP would be in accordance with Safety and Safeguards (NMSS), Division of Subpart L. Conversely,if an LTP were Waste Management, Low-Level Waste and submitted while the spent fuel was stored in Decommissioning Projects Branch is accordance with the Part 50 license, Subpart G responsible for reviewing the LTP, and of 10 CFR Part 2 would apply.
developing this Standard Review Plan (SRP).
Even after the LTP has been approved,10 The SRP guides staff reviewers in NMSS on CFR 50.59 continues to apply, to allow the performing safety reviews of LTPs. Although 1
Draft NUREG-1700
i the SRP is intended to be used by the NMSS summary is not designated " Area of Review,"
staff in conducting reviews, it can be used by as described in detailin DG-1078, interested parties responsible for conducting their own licensing reviews or developing an (2) Acceptance Critena LTP. The principal purpose of the SRP is t This section contains the technical bases for ensure the quality and unifornuty of staff determining the acceptability of analysis or of reviews and to present a well-defined base the program. The technical bases may consist from which to evaluate the requirements. It is of specific criteria, such as NRC regulatory also the purpose of the SRP to make the guides, industy codes and standards, and mformation about regulatoiy matters widely branch technical positions. These approaches available to improve the understandm, g of the are codified in this form so the staff can take staff's review process by interested members consistent positions on similar problems as of the public and the nuclear mdustry.
they arise. Branch technical positions present approaches that are acceptable to the staff for' The reviewis primarily based on the demonstrating compliance with NRC information submitted by an applicant in the regulatory requirements, but that are not LTP. The LTP must be sufficiently detailed to considered as the only possible approaches.
permit the staff to independently verify that Applicants proposing approaches to problems -
the facility can be decommissioned safely, and other than those described in the branch the license can be terminated. The specific technical positions may expect longer review infonnation that the staff needs in order to times and more extensive questioning in evaluate an LTP is identified in draft these areas.
Regulatory Guide DG-1078," Standard Format and Content of License Termination (3) Evaluation Findings Plans for Nuclear Power Reactors" (Ref. 6).
The individual SRPs are keyed to DG-1078.
This section presents the type of conclusion that is sought for the particular review area.
For each SRP, a conclusion of this type will be The SRP is wntten to cover a variety of h.eense included in the safety evaluation (SE). The termination conditions. Each SRP presents SE also will contain a description of the the acceptance entena for all areas of review review, including aspects of the review that for beense termination. For any given were selected or emphasized, and the bases i
application, the staff reviewers may select and for any deviation from the SRP.
emphasize particular aspects of each SRP as is appropriate. In some cases, a facility feature (4) Implementation may be sufficiently similar to a feature previously reviewed so that a complete new This section explains how and when the SRP review is not needed. The SRP identifies the and acceptance entena will be implemented matters to be reviewed, the basis for the by the staff.
review, and the conclusions that are sought.
(5) References Each SRP is divided into the following This section lists the references that are sections:(1) Area of Review,(2) Acceptance applicable to the review process.
Criteria, (3) Evaluation Findings, (4)
Implementation, and (5) References.
B. LTP STANDARD REVIEW PLAN AND ACCEPTANCE (1) Area of Review CRITERIA Each subsection in Section B, "LTP Standard 1.
GENERALINFORMATION Review Plan and Acceptance Criteria,"
summarizes the purpose of the review and the The LTP table of contents should address each i
applicable NRC requirements. The initial of the following 10 CFR 50.82(a)(9) criteria, Draft NUREG-1700 2-
E and the 10 CFR Part 20, Subpart E related updated site-specific estimate of j
radiological criteria for unrestricted or remaining decommissioning costs; restricted release of the site, with any supportinginformation. The regulations supplement to the environmental report, applicable to this review are 10 CFR Pursuant to 10 CFR 51.53(d), that 4
50.82(a)(9),10 CFR 50.82(a)(10), and 10 CFR describes any newinformation or j
Part 20, Subpart E.
sigmficant environmental changes associated with the licensee's proposed ACCEPTANCE CRITERIA termination activities.
2.
SITE CHARACTERIZATION The LTP is submitted in the form of a supplement to the FSAR and is accompanied Site characterization is provided to determine or preceded by an application for license the extent and range of radioactive termination.
contamination on site, including structures, systems, components, residues, soils, and The LTPis submitted two years or more surface and ground water. On the basis of the before the termination date of the license.
site characterization, the final surveys are conducted to cover all areas in which The LTP is submitted in the form of a license contamination previously existed, remains, or amendment request.
has the potential to remain. As part of the review, the NRC staff should review the The LTP lists the licensee's name and address, licensee's site characterization plans and site license number, and docket number, and that records as required under 10 CFR 50.75(g) to information ar,rees with the most recent ensure that the site characterization provided j
license.
in the LTP is complete and that the data were obtained with sufficiently sensitive instruments The LTP addresses each of the following 10 and using proper quality assurance procedures CFR 50.82(a)(9) criteria, and the 10 CFR Part to obtain reliable data applicable to 20, Subpart E, radiological criteria for determiningif the site will meet the unrestricted or restric'.ed release of the site:
decommissioninglimits. The regulation applicable to this area of review is 10 CFR site characterization; 50.82(a)(9)(ii)(A).
identification of remaining site ACCEPTANCE CRITERIA dismantlement activities; The LTP identifies all locations, inside and plans for site remediation; utside the facility, where radiological spills, disposals, operational activities, or other ra acciden i cident at ed etailedplans or 1 radiation surveys structures, equipment, laydown areas, or soils method for demonstrating compliance (subfloor and outside area).
with the radiological criteria for license The LTP describes,in a summary form, the termination; original shutdown and current radiological and j
non-radiological status of the site.
For restricted release, the LTP should contain a description of the site's end use, The LTP site characterization is sufficiently documentation on public consultation, detailed to allow NRC to determine the extent institutional controls, and financial and range of radiological contamination of assurance needed to comply with the structures, systems (including sewer systems, requirements for license termination for and waste management systems), floor drains, restricted release or alternate criteria.
ventilation ducts, piping and embedded piping, 3
Draft NUREG-1700 l
rubble, contamination on and beneath paved The LTP contains a listing of the remaining parking lots, ground water and surface water, activities that do not involve unreviewed safety components, residues., and environment, questions or changes in a facility's technical including maximum and average specifications; this list should be of sufficient contamination levels and ambient exposure detail for the staff to confirm that remediation rate measurements of all relevant areas activities may in fact be carried out in (structures, equipment, and soils) of the site.
accordance with 10 CFR 50.59.
The LTP should identify the survey 4.
REMEDIATION PLANS instruments and supporting quality assurance The LTP discusses in detail how facility areas practices used in the site characterization and site areas will be remediated to meet NRC Program.
release criteria. The regulations applicable to this area of review are 10 CFR The LTP is sufficiently detailed to provide data for planning further decommissioning 50.82(a)(9)(ii)(C) and 10 CFR Part 20, activities, which include decontamination Subpart E (Ref. 3).
techniques, projected schedules, costs, waste ACCEPTANCE CRITERIA volumes, dose assessments (including ground-water assessments), and health and The LTP addresses any changes in the safety considerations.
radiological controls to be implemented for the control of radiological contamination 3.
IDENTIFICATION OF REMAINING associated with remaining decommissioning SITE DISMANTLEMENT ACTIVITIES and remediation activities.
The LTP describes the remaining site.
The LTP discusses in detail how facility areas dismantlement activities. The regulation and site areas will be remediated to meet the a
area of reviewis 10 CFR gP Subpart E of 10 CFR Part 20 (Ref. 3).
NRC.riteria for license termination in ACCEPTANCE CRITERIA Discussions should focus on any unique techniques or procedures used to evaluate the The LTP discusses the remaining tasks effectiveness of remediation, including any associated with the decontamination and computer modeling programs.
dismantlement, estimates the quantity of If the end use of the site is for restricted radioactive material to be released t release, the LTP should discuss, in detail, unrestricted areas, de, scribes the proposec.
control mechamsms to ensure areas are r,t dose-modeling projections and institutional recontaminated, and contains occupational controls to be put into place over the site.
exposure estimates and radioactive waste 5.
FINAL RADIATION SURVEY PIAN charactenzat on.
i The LTP describes the final survey plan for The LTP describes in detail the creas and confirming that the plant and site will meet the equipment that need further rem:diation to restricted or unrestricted release criteria. The allow the reviewer to estimate the radiological regulations applicable to this area of review conditions that will be encountered during are 10 CFR 50.82(a)(9)(ii)(D) and 10 CFR remediation of equipment, components, 20.1501(a) and (b). The final status survey is structures, and outdoor areas.
the radiation survey performed after an area l
has been fully characterized, remediation has The LTP describes the remaining been completed, and the area is ready to be dismantlement activities in sufficient detail for released. The purpose of the final status NRC to identify any inspection or technical survey is to demonstrate that the area resources needed during the remaining conforms to the radiological criteria for dismantlement activities.
license termination. The final status survey is DrMt NUREG-1700 4
1
l not conducted for the purpose oflocating the identification of the major a
residual radioactivity; the historical site radiological contaminants; assessment and the characterization survey perform that function. This section of the methods used for addressing
=
SRP endorses the final survey status methods hard-to-detect radionuclides; described in Chapter 2 of draft Regulatory Guide DG-4006,"Demonstratmg access control procedures to control recontamination of clean areas.
Compliance With the Radiological Criten. for a
License Termination" (Ref. 4), for The licensee's final radiation survey plan demonstrating compliance with Subpart E of describes the scope of the survey and the 10 CFR Part 20.
general procedures followed, including survey procedures to ensure that the survey ACCEPTANCE CRITERIA techniques and instrument sensitivity are appropriate for measuring the major The LTP is acceptable if the final survey plan radiological contaminants identified, and how addresses,in a manner consistent with draft the plan will demonstrate that the plant and Regulatory Guide DG-4006, the following site will meet criteria for release for license items, which are not meant to be all inclusive:
termmation.
The LTP is acceptable if the licensee has the methods proposed for surveying all appropriately divided the survey area into eqmpment, systems, structures, and soils survey units.
(diagrams, plot plans, and facility layout drawings should be used to facilitate The LTP is acceptable if the final survey plan, presentation), as well as a method for consistent with draft Regulatory Guide ensuring that sufficient data are included DG-4006, identifies the scanning to be for a meaningful statistical survey; performed to locate small areas of elevated concentrations of residual radioactivity to a description of the methods to be used to determine whether they meet the radiological e
establish background radiation levels; criteria for license termination; commits to perform scanning in each survey unit to detect a description of the Quality Assurance areas of elevated concentrations; and (QA) Program, to support both field establishes investigation levels for survey work and laboratory analysis, that investigating significantly elevated addresses the QA organization; training concentrations of residual radioactivity.
and qualification requirements; survey mstructions and procedules, including The LFP is acceptable if the final survey plan water, air, and soil samphng procedures; addresses the presence of subsurface residual document control; control of purchased radioactivity. Subsurface residual radioactisity items; inspections; control of survey is mainly determined by the historical site eqmpment; handling, storage, calibration, assessment, with knowledge of how the and response checks; shipping of survey residual radioactivity was deposited.
equipment and laboratory samples; The LTP fm' al survey plan is acceptable if the nonconformance items; corrective action; licensee establishes, consistent with the QA records; and the survey audits, guidance in draft Regulatory Guide including methods to be used for DG-4006, a reference coordinate system for reviewing, analyzing, and auditing data; the survey areas. A reference coordinate system is a set ofintersectinglines referenced verification surveys and evaluations used to a fixed site location or benchmark.
to support delineation of radiologically Reference coordinate systems are established affected (contaminated) areas and so that the locations of any point in the survey unaffected (noncontaminated) areas; unit can be identified by coordinate numbers.
5 Draft NUREG-1700 1
I.
1 A reference coordinate system does not 25-mrem-per-year criterion. Draft establish the number of sample points or Regu'atory Guide DG-4006, determine where samples are taken. A single
" Demonstrating Compliance With the reference coordinate system may be used for a Radiological Criteria for License site, or different coordinate systems may be Termination" (Ref. 4), provides additional used for each survey unit or for a group of guidance, acceptable to the NRC staff, on survey units how to demonstrate compliance with the unrestricted release criteria. Draft 6.
COMPLIANCE WITH THE Regulatory Guide DG-4006 also RADIOLOGICAL CRITERIA FOR provides guidance on conducting dose LICENSE TERMINATION modeling, use of generic screening The licensee needs to clearly present in the methods, use of site-specific parameter LTP the radiological criteria proposed for values and alternate models, use of license termination. If a licensee desires an computer models, and methods for unrestricted release per 10 CFR Part 20, conducting a final survey.
Subpart E (Ref. 3), the licensee should The LTP describes acceptable methods desenbe the methods used to demonstrate for calculating DCGL values, methods for compliance. If a licensee requestslicense calculating site-specific DCGL values for termmation under the restricted release buildings and soil, methods for calculating enteria per Subpart E of 10 CFR Part 20 (Ref.
area factors for use with the elevated 3), the LTP should describe in detail how the measurement comparison, and methods requirements of 10 CFR 20.1403 and 10 CFR for handling special circumstances in 50.82(a)(9)(ii)(E) will be met. If a licensee buildings and soils.
requests license ternunation under the alternate radiological criteria in 10 CFR The LTP includes justification for the use 20.1404, the LTP should describe how the of the default scenarios and parameters requirements in 10 CFR 20.1301(a)(1),10 for the DandD code consisting of a CFR 20.1404, and 10 CFR 50.82(a)(9)(ii)(E) statement that no other conditions are will be met.
reasonably expected to exist at the site except for those incorporated in the ACCEPTANCE CRITERIA default scenarios and modeling assumptions, that would cause a For unrestricted release, the LTP is acceptable significant increase in the calculated dose.
If If DandD is ased to estimate the DCOL, the licensee should send the NRC a copy The licensee demonstrates that the dose of the report produced by DandD to from residual radioactivity that is verify the version of DandD that was used distmguishable from background in the analysis. Information on site radiation results m a total effective dose characterization should be submitted to equivalent (TEDE) to an average show that DandD is applicable for the site member of the entical group (DCGL, the conditions.
desired concentration guideline) that does not exceed 25 mrem (0.25 mSv) per year The LTP demonstrates compliance by over a 1000-year period, including the using NRC's screening models and 1
dose from ground water sources of parameter values, and progression to drinking water. The LTP also more site-specific analysis is unnecessary.
demonstrates that residual radioactivity The licensee need only provide has been reduced to levels that are as low site-specific final status survey results that as is reasonably achievable (ALARA).
are compared with the generic DCGL. If The LTP should describe in detail the other computer models are used to methods and assumptions used to estimate the DCOL, the licensee should demonstrate compliance with the provide sufficient information to the NRC -
Draft NUREG-1700 6
1
=
l to allow review of the model, scenarios, The licer see demonstrates that furtia and parameters.
reductions in residual radioactivity necessary to release the site for If the LTP demonstrates compliance by unrestricted use (1) would result in net using site-specific information to derive Public or emironmental harm or (2) were DCGLs, the licensee should justify the not being made because the residual site-specific parameter values and levels are AIARA.
alternative models. Site-specific scenarios The licensee describes in detail the to calculate doses from residual methods and assumptions that will be radioactivity m soil should describe the.
used :o demonstrate that the licensee will reasonable land uses and human activities
.or the future, following license provide reasonable assurance that the termination. It is reasonable to assume dose from residual radioactivity, that current land uses in the area will be distinguishable from background continued for the period of the dose radiation, will not exceed 25 mrem per assessment (1000) ears). If a site-specific year to a member of the critical group, over a 1000-year peried, with the scenario or screemng group will.: used for structures, a description of the restrictions in place.
reasonable use of the structure after The licensee has made provisions for license termination for the projected legally enfcrceable institutional controls lifetime of the structure should be that would limit the dose to the average provided. If the lifetime cannot be member of the critical group to 25 mrem estimated,70 years may be used.
(0.25 mSv) p:r year.
The licensee has provided sufficient The LTP demonstrates whether it is feasible to further reduce the levels of financial assurance to enable an residual radioactivity to levels below those independent third party to assume and necessary to meet the dose criteria (i.e.,
carry out responsibilities for any i
to levels that are ALARA). Draft necessary control and maintenance of Regulatory Guide DG-4006 (Ref. 4) the site.
describes methods acceptable to the NRC The licensee has submitted to the NRC a staff for determining when it is feasible t further reduce the concentrations of license termination plan that indicates the licensee's intent to release the site under residual radioactivity to below the restricted conditions and tells how advice concentrations necessary to meet the dose criteria.
from individuals and institutions in the community that may be affected by the decommissioning has been sought and For restricted release, the LTP is acceptable if incorporated, as appropriate, following it addresses the criteria identified that follow.
analysis of that advice.
In addition to the criteria identified below, draft Regulatory Guide DG-4006, The licensee demonstrates that the
" Demonstrating Compliance With the residual radioactivity levels have been Radiological Criteria for License Termination" reduced so that,if the institutional (Ref. 4), prmides additional guidance, controls were no longer in effect, the acceptable to the NRC staff, on how to annual dose to the average member of the
?
demonstrate compliance with license critical group would not exceed either 100 termination restricted release criteria. Note mrem (1 mSv) or, under certain that sites requesting consideration for conditions,500 mrem (5 mSv). If the restricted release will be included in the 500-mrem /yr (5 mSv/yr) value is used, the NRC's Site Decommissioning Management licensee must (1) demonstrate that Plan.
achieving 100 mrem /yr is prohibitively 7
Draft NUREG-1700
expensive, not technically achievable, or under restricted conditions; and any would result in net harm, (2) make Indian tribe or other indigenous people provisions for durable institutional who have relevant treaty or statutory controls, and (3) provide sufficient rights that may be affected by the financial assurance to allow an decommissioning of the site.
independent third party to recheck the The licensee demonstrates that it controls at least every 5 years.
provided a comprehensive, colk.tive If the annual dose to the average member discussion on the issues with represented of the critical group would not exceed 100 Participants, and provided a publicly mrem (1 mSv)if the institutional controls available summary of the results that were no longer in effect, the licensee contained a description of the viewpoints chooses a private individual, organization, of the participants on the issues, and a or State or 'ocal government as the party description of the extent of the agreement responsible for enforcing the institutional or disagreement among the participants control.
on the issues.
The licensee describes the site end use for The licensee demonstrates that when the annual dose could exceed 100 mrem (I any areas proposed for restricted release.
mSv) but be less than 500 mrem (5 mSv),
if the mstitutional controls were no longer For license termination using alternate in effect, a more durable m, stitutional criteria, the LTP is acceptable ifit addresses the criteria identified below. In addition to control will be used, i.e.,10 CFR 20.1403(c). To meet the ctirement in the criteria identified below, draft Regulatory 10 CFR 20.1403(e), an mstit tional Guide DG-4006," Demonstrating control that mvolves government Compliance With the Radiological Criteria for ownership ofland would be generally License Termination" (Ref. 4), provides acceptable or an institutional control on additional guidance, acceptable to the NRC privately owned land with a State or local staff, on how to demonstrate compliance with government as the party responsible for the license termination using alternate enforemg the restriction could also be criteria. Note that the NRC staffis required i
to consult with the Environmental Protection I
acceptable, depending on the Agency (EPA), and to obtain Commission circumstances at the site.
approval of the use of the alternate criteria consistent with 10 CFR 20.1404 and 1405. The The licensee identifies the affected e
parties. According to 10 CFR SUPPortmg analysis includes an evaluation of 20.1403(d)(2), the licensee must provide Public comments and EPA's comments.
for participation by representatives of a The licensee proposing to use alternate broad cross-section of the community who criteria would have to present a complete may be affected by the decomnussioning.
and comprehensive analysis of such Affected parties may mclude any State mssible sources of exposure.
agency, local agency, or Federal Government agency, other than the NRC, The licensee would employ, to the extent that has jurisdiction or responsibilities practical, restrictions on site use for with respect to the site to be minimizing exposure at the site, using the
)
decommissioned; local conununity, civic, provisions for institutional controls and labor, or emironmental organizations financial assurance in 10 CFR 20.1403.
with an interest in the decommissioning, I
and whose members would be affected by The licensee-supporting analysis would the decommissioning; adjacent demonstrate that the residual landowners whose property abuts the site radioactivity levels have been reduced so or portions of the site to be released that it is unlikely that the annual dose Draft hUREG-1700 8
t from all man-made sources combined, assurance instrument required under 10 CFR other than medical, to the average 50.75 must be funded to the amount of the member of the critical group would not cost estimate. If there is a deficit in current exceed 100 mrem (1 mSv).
funding, the LTP must indicate the means for ensuring adequate funds to complete The licensee would reduce doses to decommissioning. The regulation applicable
=
ALARA levels, on the basis of a to this area is 10 CFR 50.82(a)(9)(ii)(F).
comprehensive analysis of risks and benefits of all viable alternatives.
ACCEPTANCE CRITERIA The licensee would seek advice from The LTP decommissiomng cost estimates are affected parties regarding the use of acceptab"if theyinclude an evaluation of the alternate criteria at the site. In seeking followint cost elements identified below. In this advice, the licensee would conduct addition, Regulatory Guide 1.159," Assuring the activities for seeking advice required the Avanotibtv : f Funds wr Decommissiomng by 10 CFR 20.1404(a)(4), including Nuclear Reactors'- (Pef. 7), provides a providing for participation by a broad detailed explanation of methods for estimating cross-section of the community who may decommissioning costs, as well as accepted be affected by decommissioning, financial assurance mechanisms.
providing an opportunity for a comprehensive collective discussion of the Cost Elements issues related to the alternate criteria by the affected parties, and providing a e st assumptions used, m. eluding a publicly available summary of all such contingency factor discussions. As part of this process, th?
licensee would submit a decommissiomng major decommissioning activities and tasks plan or LTP indicating how advice from individuals and institutionsin the unit cost factors a
community that may be affected by the decommissioning has been sought and estimated costs of decontamination and addressed.
removal of equipment and structures The licensee proposing to use alternate estimated costs of waste disposal, criteria has provided a complete and including applicable disposal site comprehensive analysis of such possible surcharges and transportation costs sources of exposure.
estimated final smvey costs The licensee describes the site end use for any areas proposed for restricted release.
estima.ed total costs 7.
UPDATE OF THE SITE-SPECIFIC The LTP focuses on detailed DECOMMISSIONING COSTS activity-by-activity cost estimates.
The LTP must provide an estimate of the The LTP compares the available funds for the remaining decommissioning cost for decommissioning with the calculated total cost unrestricted or restricted release of the site.
from the licensee's detailed cost analysis.
The LTP should compare the estimated cost with the present funds set aside for The LTP cost estimates for decommissioning decommissioning, and should note how are based on credible engineering decommissioning financial assurance assumptions, and the assumptions are related instruments required under 10 CFR 50.75 will to all major remaining decommissioning be increased,if necessary. The financial activities and tasks.
9 Draft NUREG-1700
The LTP cost estimate is acceptable if it C. EVALUATION FINDINGS includes the cost of the remediation action being evaluated, the cost of transportation and disposal of the waste generated by the action, The licensee's termination plan demonstrates and other costs that are appropriate for the that the remainder of the decommissionmg specific case. The current version of activities will be performed m, accordance with NUREG-1307," Report on Waste Burial the regulations, will not be harmful to the Charges" (Ref. 8), provides guidance on common defense and security or to the health estimating waste disposal costs.
and safety of the public, and will not have a significant deleterious effect on the quality of 8.
SUPPLEMENT TO THE the emironment.
ENVIRONMENTAL REPORT The conclusions are as follows:
The licensee must submit a supplement to the environmental report describing any new (1) The licensee has submitted the LTP as a information or significant environmental supplement to the facility's FSAR on its change associated with the site-specific equivalent according to 10 CFR termination activities. The regulations 50.82(a)(9)(i).
applicable to this area of review are 10 CFR 50.82(a)(9)(ii)(G) and 10 CFR 51.53.
(2) The licensee has met the objective of providing an adequate site ACCEPTANCE CRITERIA characterization (radiological and non-radiological) as required by 10 CFR The supplement to the environmental report 50.82(a)(9)(ii)(A).
describes proposed termination activities resulting in significant environmental changes (3) The licensee has identified the remaining not bounded by the site-specific dismantlement activities that are decommissioning activities described in the necessary to complete the PSDAR, the previously issued environmental decommissioning of the facility / site, as assessment, or the emironmental impact required by 10 CFR 50.82(a)(9)(ii)(B).
statement. The supplement to the environmental report will be acceptable if the (4) The licensee has adequatelyidentified all discussed proposed impacts are bounded by site areas requiring remediation and has the impacts in NUREG-0586 (Ref. 9), the in place an organization to safely perform PSDAR, the previc,asly issued environmental the remediations as required by 10 CFR assessment, or the environmentalimpact 50.82(a)(9)(ii)(C). The licensee has met statement, the requirements of 10 CFR Part 20 and the applicable disposal site license The supplement to the environmental report conditions for proce.aing, transport, and describes the impacts associated with those disposal of low-levet radioactive waste.
site-specific termination activities, compares the impact with previously analyzed (5) The licensee has conformed to 10 CFR termination activities, and analyzes the 50.82(a)(9)(ii)(D)in that the final emiromnentalimpact of the site-specific radiation survey plan in the LTP provides activity.
assurance that residual radioactive contamination levels will meet 10 CFR J
The supplement to the environmental report Part 20, Subpart E.
I describes changes to the data since the I
issuance of the PSDAR and the updated (6) The licensee has met the requirements of "Emironmental Report Operating License 10 CFR 50.82(a)(9)(ii)(E), with respect to Stage" related to the site location, climate, prmiding a description of the end use of demography, socioeconomic data, land use, the. site,if restricted, surface water, grcund water, and biota.
Draft NUREG-1700 10
6 (7) The licensee has met the requirements of (15) The licensee has conformed to 10 CFR 10 CFR 50.82(a)(9)(ii)(F), with respect to 20.1404(a)(4)in that the LTP providing an updated site-specific demonstrates that the requirements estimate of the remaining related to public involvement criteria for decommissioning costs, and plans for license termination using alternate ensuring the availability of adequate criteria have been met.
funds for decommissioning (16) The decommissioning alternative provides (8) The licensee has conformed to 10 CFR for completion of decommissioning within 20.1402 in that the LTP demonstrates that 60 years, as required by 10 CFR the radiological criteria for unrestricted 50.82(a)(3). If the decommissioning release will be met, alternative res tits in delay of completion of decommisooning for more than 60 (9) The licensee has conformed to 10 CFR years, the license has justified the delay in g
20.1403(a) in that the LTP demonstrates accordance with 10 CFR 50.82(a)(3).
that further reductions in residual radioactivity necessary to release the site (17) The licensee has met the requirements of for unrestricted use (a) would result in Part 51 by providing acceptable updates to net public or environmental harm or (b) the "Emironmental Report were not being made because the residual Post-Operating License Stage."
levels are ALARA.
(10) The licensee has conformed to 10 CFR D.
IMPLEMENTATION 20.1403(b) in that the LTP demonstrates that the dose criteria for restricted This SRP will be used to provide information release, with the institutional controls in to licensees regarding the staff's plans for place, will be met.
evaluating conformance of LTP submittals including submittals in acceptable alternative (11) The licensee has conformed to 10 CFR formats with Commission regulations.
20.1403(c) in that the LTP demonstrates that sufficient financial assurance is The provisions of this SRP apply to submittals available if a third party had to assume made after the date ofissuance of this SRP.
and carry out any necessary maintenance at the site.
E.
REFERENCES (12) The licensee has conformed to 10 CFR 20.1403(d)in that the LTP demonstrates 1.
U.S. Nuclear Regulatory Commission, that the requirements related to public
" Decommissioning of Nuclear Power involvement criteria for license Reactors" (10 CFR Parts 2. 50, and 51),
termination for restricted release have Federal Register, Vol. 61, pp. 39278-39304 been met.
(61 FR 39278), July 29,1996.
(13) The licensee has conformed to 10 CFR 2
U.S. Nuclear Regulatory Commission, 20.1403(e) in that the LTP demonstrates Draft Regulatory Guide DG-1067, that the dose criteria for restricted
" Decommissioning of Nuclear Power release, when the institutional controls Reactors," June 1997.
fail, will be met.
3.
U.S. Nuclear Regulatory Commission, (14) The licensee has conformed to 10 CFR
" Radiological Criteria for License 20.1404(a) in that the LTP demonstrates Termination" (10 CFR Parts 20,30,40, that the dose criteria for license 50,51, 70, and 72), FederalRegister, Vol.
terrrination using alternate criteria will be 62, pp. 39058-39092 (62 FR 39058),
met.
July 21,1997.
11 Draft NUREG-1700
4.
U.S. Nuclear Regulatory Commission, Termination Plans for Nuclear Power Draft Regulatory Guide DG-4006, Reactors," April 1998.
" Demonstrating Compliance With the Radiological Criteria for License 7.
U.S. Nuclear Regulatory Commission, Termination," August 1998.
Regulatory Guide 1.159, " Assuring the Availability of Funds for Decommissioning Nuclear Reactors."
5.
U.S. Nuclear Regulatory Commission, Draft Regulatory Guide DG-1071, 8.
U.S. Nuclear Regulatory Commission,
" Standard Format and Content Guide for NUREG-1307, Rev. 8, " Report on Waste Post Shutdown Decommissioning Burial Charges," December 1998.
Activities Report," December 1997.
9.
U.S. Nuclear Regulatory Commission, NUREG-0586," Final Generic 6.
U.S. Nuclear Regulatory Commission, EnvironmentalImpact Statement on Draft Regulatory Guide DG-1078, Decommissioning of Nuclear Facilities,"
" Standard Format and Content of License August 1998.
Draft NUREG-1700 12
NRCFORM 33s U.S. NUCLEAR REGULATORY eruanasam
- 1. REPORT NuMaER
. om pemenee av NRc, Am va., supp, nov, EE BIBUOGRAPHIC DATA SHEET
"^"*"'""'"""**'*"*"'I (See hshciens on me reverse) 2 *nTLE ANDSUBN NUREG-1700 Standard Review Plan for Evaluating Nuclear Power Reactor License Termination Plans l
MOMTH YEAR Draft Reportfor Comment December 1998
- 5. AUTHOR (S)
- 6. TYPE OF REPORT C.L Pittigli Draft
- 7. PERIOD COVERED (ancark Dease)
- 8. PERFORhaNG ORGANIZATION. NAhE AND ADDRESS (FMtC, pwaie Dys.m Omco a Aspen, U.S. NucJesr Ampudskry Commasert ansf me&ng ad&ess,- #contactr.
pane name amt mesne sneen)
Division of Waste Management Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
- 9. SPONSORING ORGANIZATION NAhE AND ADDRESS (r ARC, type "seme as enove; scontecer, pode Mtc Dween, cerce or Aspert u.s. Nucasse Assuasary canmesmet omt meene ed*ess)
L',ame as 8. above.
- 10. SUPPLEhF.NTARY NOTES
- 11. ABSTRACT (200 worsa er asas)
The standard review plan (SRP) guides NRC staff in performing safety reviews of license termination plans (LTPs). Although interested parties can use it for conducting their own licensing reviews or developing an LTP, the principal purpose of the SRP is to ensure the quality and uniformity of NRC staff reviews and to present a well-defined base from which to evaluate the requirements for termulating the license of a nuclear power plant. It is also the purpose of the SRP to make the information about regulatory matters widely available in order that interested members of the public and the nuclear industry gain a better understanding of the staffs review process. Each SRP presents the acceptance criteria of at areas of review for license termination. The SRP identries the matters to be reviewed, the basis for the review, and the conclusions that are sought.
- 12. IEY WORDS/DET>CRIPTORS g.Jaf words erpareses met we esamtnemeneners e 4xzeng aw remut)
- 13. AVALABluTY STATEMENT Decommissioning License Termination Plans Unlimited 14 SECURfrYCLASSFICATION (The Page)
Unclassified (nusAeown Unclassified
- 15. NuMSER OF PAGES
- 16. PRICE NRCIORM S36 (2 89)
j Printed l
on recycled Paper Federal Recycling Program
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