ML20203B806
| ML20203B806 | |
| Person / Time | |
|---|---|
| Issue date: | 01/31/1999 |
| From: | NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | |
| References | |
| TASK-*****, TASK-RE REGGD-01.179, REGGD-1.179, NUDOCS 9902110014 | |
| Download: ML20203B806 (8) | |
Text
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U.S. NUCLEAR REGULATORY COMMISSION January 1999
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REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 1.179 (Draft was issued as DG-1078) l STANDARD FORMAT AND CONTENT OF LICENSE TERMINATION PLANS FOR NUCLEAR POWER REACTORS A. INTRODUCTION the initial activities and the major phases of decommis-sioning.
On July 29,1996, the NRC published amendments For Phase 3,10 CFR 50.82(a)(9) specifies that an to its regulations in 10 CFR Part 2," Rules of Practice application for license termination must be accompa-for Domestic Licensing Proceedings and Issuance of nied or preceded by a license termination plan (LTP),
Orders"; 10 CFR Part 50," Domestic Licensing of Pro-which is subject to NRC review and approval. Accord-duction and Utilization Facilities"; and 10 CFR Part 51, ing to 10 CFR 50.82(a)(9)(i), the licensee must submit
" Environmental Protection Regulations for Domestic an LTP at least two years before termination of the li-Licensing and Related Regulatory Functions"(61 FR cense. The LTP is approved by license amendment. A 39278)(Ref.1). These amendments prescribsspecific public meeting must be held near the site; any hearing criteria for decommissioning nuclear power reactors; held in relation to the LTP would fall under either Sub-(m f
") inating, revising, or extending operating reactor requi-they were effective August 20,1996. This rule, by elim-part G or Subpart L of Part 2. If the fuel has been perma-nently removed from the Part 50 facility to an autho-rements commensurate with their importance to safety, rized facility, a hearing for the proposed LTP would be specifies requirements for reactors that are permanently in accordance with Subpart L. Conversely,if an LTP shut down and have no fuel in the reactor vessel. Reac-were submitted while the spent fuel was stored under tors that are permanently shut down with no fuel in the the Part 50 license, Subpart G of 10 CFR Part 2 would vessel present a significantly reduced risk to the public, apply.
Decommissioning activities for power reactors Even after the LTP has been approved,10 CFR may be divided into three phases: (1) initial activities, 50.59 continues to apply to allow the licensee to make (2) major decommissioning and storage activities, and certain changes that do not result in an unreviewed (3J license termination activities. Draft Regulatory safety questmn or changes to the techmcal specifica-Guide DG-1067, " Decommissioning of Nuclear tions, and the changes must meet the requirements of Power Reactors" (Ref. 2), is being developed to de-10 CFR 50.82(a)(6).
scribe methods and procedures that are acceptable to On July 21,1997, the Commission amended its the NRC staff for implementing the rules that relate to regulations in 10 CFR Part 20," Standards for Protec-USNRC REGULATORY GUIDr3 Tre guides are is.ued in lhe follomng ten broad dnnson.
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tion Against Radiation"; 10 CFR Part 30, " Rules of low from 10 CFR 50.82(a)(9),10 CFR 50.82(a)(10),
General Applicability to Domestic Licensing of By-and the related radiological criteria from Subpart E of product Material"; 10 CFR Part 40," Domestic Licens-10 CFR Part 20 for unrestricted or restricted release of ing of Source Material"; 10 CFR Parts 50 and 51; the site. The LTP should include any supporting infor-10 CFR Part 70," Domestic Licensing of Special Nu-mation necessary to address the criteria, such as:
clear Material"; and 10 CFR Part 71," Packaging and Site characterization Transportation of Radioactive Material"(62 FR 39058, Ref. 3), prescribing specific radiological criteria for li-M*".tification of remaining site dismantlement ac-tivities cense termination. Draft Regulatory Guide DG-4006, Plans for site remediation
" Demonstrating Compliance With the Radiological Criteria for Licence Termination"(Ref 4),is being de-Detailed plans for the final radiation survey for re-veloped to provide additional guidance on demonstrat-lease of the site ing compliance with the unrestricted release, restricted Method for demonstrating compliance with the ra-release, and alternative criteria for license termination diological criteria for h,eense termination. For re-in accordance with Subpart E of 10 CFR Part 20.
stricted release, the LTP should include a descrip-Under the new regulations, in the LTP a licensee tion of the site's end use, documentation on public I
could propose either release of the facility and site for consultation, institutional controls, and financial unrestricted use or release of the facility and site under assurance needed to comply with the requirements restricted use conditions.
for license termination for restricted release or al-For the most part, the LTP will contain a final site l
characterization, dose assessment, identification of the Updated site-specific estimate of remaining de-remaining remediation activities and supporting plan, commissioning costs and final survey plan. The LTP must be submitted as Supplement to the environmental report, pursuant a supplement to the licensee's final safety analysis re-to 10 CFR 51.53, that describes any new informa-port (FSAR) or as an equivalent document. A licensee tion or significant environmental changes associ-might submit the ITP concurrently with the post-ated with the licensee's proposed termination ac-shutdown decommissioning activities report tivities.
l (PSDAR). Guidance is being developed on the content 2.
SITE CllARACTERIZATION of the PSDAR and is proposed in draft Regulatory Guide DG-1071, " Standard Format and Content for The purpose of providing information on si.e char-Post-Shutdown Decommissioning Activities Report" acterization is to ensure that final radiation surveys are (Ref. 5).
conducted to cover all areas where contamination ex-isted, remains, or has the potential to exist or remain.
This regulatory guide provides guidance on devel-The lict ssee can submit the entire site character-oping LTPs for nuclear power reactor licensees who izat. ion package separately at any time prior to submit-wish to terminate their licenses and release their sites.
tal of the LTP and reference it in the LTP, or the site The information collections contained in this regu-characterization can be submitted as an integral part of latory guide are covered by the requirements of 10 CFR the LTP.
Parts 50 and 51, which were approved by the Office of The LTP site characterization should be suffi-Management and Budget, approval numbers ciently detailed to allow NRC to detectnine the extent 3150-0011 and 3150-0021. The NRC may not conduct and range of radiological ccmtamination of structures, or sponsor, and a rerson is not required to respond to, a systems (including sewer systems, waste plumbing collection ofinformation unless it displays a currently systems, floor drains, ventilation ducts, piping and em-valid OMB control number.
bedded piping), rubble, paved parking lots (both on and B. CONTENT OF LICENSE beneath), ground water and surface water, components, TERMINATION PLAN residues, and the environment, including the maximum and average ccmtamination levels and ambient expo-sure rate measurements of all relevant areas (structures, 1.
GENERAL INFORMATION equipment, and soils) of the site. Thc site characteriza-The licensee's name, address, license number, and tion should be sufficiently detailed to provide data for docket number should agree with the most recent li-planning further decommissioning activities as well as cense. The LTP should address each of the criteria be-the final survey program.
1.179 - 2
The LTP should describe historic events (including to the radiation protection program are not required in dates, types of occurrences, locations in and outside of the LTP, but would be included in periodic updates to the facility), such as radiological spills, disposals, or the Final Safety Analysis Report.
(
other radiological accidents or incidents, that resulted The LTP should discuss in detail the remediation or could have resulted in contamination of structures, methods and techniques that will be used to demon-equipment, laydown areas, or soils (subfloor and out-strate that the facility and site areas meet the NRCerite-side area).
ria for license termination in Subpart E of 10 CFR Part The LTP should describe the survey instruments 20 (Ref. 3).
and supporting quality assurance practices used in the 5.
FINAL RADIATION SURVEY PLAN site charactenzation program. The LTP should discuss how the data quality objectives discussed in The LTP should describe the final survey plan for NUREG-1575, " Multi-Agency Radiation Survey and confirming that the plant and site will meet the re-Site Investigation Manual (M ARSSIM)"(Ref. 6), were stricted or unrestricted release criteria in Subpart E of applied during site characterization.
10 CFR Part 20 (Ref. 3) for license termination, as ap-plicable. The NRC's regulations applicable to radiolog-MARSSIM (Ref. 6) provides guidance on devel-oping a site characterization program, and further guid-ical surveys are found at 10 CFR 50.82(a)(9)(ii)(D) and ance is being developed in NRC's " Draft Branch Tech-10 CFR 20.1501(a) and (b). The final status survey is the radiation survey performed after an area has been nical Position on Site Characterization for Decommissioning"(Ref. 7 ).
fully characterized, remediation has been completed, and the licensee believes that the area is ready to be re-3.
IDENTIFICATION OF REMAINING SITE le sed.The purpase of the final status survey is to dem-I area meets me raMogmal nitsa for DISMANTLEMENT ACTIVITIES license termination. The final status survey is not con-The LTP should contain a discussion of the :emain-ducted for the parpose oflocating residual radioactiv-ing tasks associated with the decontamination and dis-ity; the historical site assessment and the characteriza-mantlement, an estimate of the quantity of radioactive tion survey perform that function. MARRSIM (Ref. 6) p material to be released to unrestricted areas, and the provides guidance on final survey methods and on de-V proposed control mechanisms, person-rem estimates, veloping a fir ' mvey plan for demonstrating com-and radioactive waste characterization. The LTP should pliance with Subpart E of 10 CFR Part 20; further guid-also identify any decommissioning tasks that require ance is proposed in Regulatory Position 2 of Draft coordination with any other Federal or State regulatory Regulatory Guide DG-4006, " Demonstrating Com-agency.
pliance with the Radiological Criteria for License Ter-In the LTP, the areas and equipment that need fur-mination"(Ref. 4). The following items, which are not ther remediation should be described in sufficient detail meant to be all-inclusive, should be included in the fi-to allow the reviewer to prdict the radiological condi-nal radhtion survey plan.
tions that will be encountered during remediation. The The methods proposed for surveying all equip-details in this section should be sufficient for the NRC ment, systems, structures. and soils (diagrams, plot te' identify any inspection or technical resources needed plans, and facility layout drawings should be used during the remaining dismantlement activities, to facilitate presentation), as well as a method for The LTP should include a list of the remaining ac-ensuring that sufficient data are included for a tivities that do not involve unreviewed safety questions meanmgful statistical survey.
or changes in a facility's technical specifications, and A description of the methods to be used to establish this list should be sufficiently detailed for the staff to background radiation levels (variances in back-confirm that remedial activities may in fact be carried ground radiation can be expected between struc-out under 10 CFR 50.59.
tures constructed of different materials) (Ref. 8).
4.
REMEDIAT!ON PLANS A description of the quality assurance (QA) pro-gram to support both field survey work and labora-The LTP should summarize any changes from the tory analysis that addresses the OA organization; previously approved radiological control program that training and qualification requirements; survey in-(Vy) will be used for the control of radiological contamina-structions and procedures including water, air, and tion associated with the remaining decommissioning soil sampling procedures; document control; con-and remediation activities. Details regarding changes trol of purchased items; inspections; control of sur-1.179 - 3
vey equipment; handling, storage, and response terim guidance on an acceptable methodology for cal-checks; shipping of survey equipment and labora-culating dose.
tory samples; nonconformance items; corrective action; QA records; and survey audits, including if a licensee requests license termination under the methods to be used for reviewing, analyzing, and restricted release criteria per Subpart E of 10 CFR auditing data.
Part 20 (Ref. 3), the LTP should describe in detail the Verification surveys and evaluations used to sup-methods and assumptions that will be used to demon-
=
i port delineation of radiologically affected (con.
strate that the licensee will provide reasonable assur-
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taminated) areas and unaffected (uncontaminated) ance that the dose from residual radioactivity distin-guishable from background will not exceed 25 mrem l
areas.
per year to a member of the critical group over a identification of the major radiological contami-1000 year period with the restrictions in place (10 CFR
=
nants.
20.1401(d) and 10 CFR 20.1403(b)). The LTP should Methods used for addressing hard-to-detect radio-discuss site end use, the institutional controls to be put a
in place, and the maintenance required for the controls nuclides.
(including financial assurance for any necessary con-Access control procedures to control recontamina-trol and maintenance of the site) until the residual radio-l l
tion of clean areas.
activity meets unrestricted release criteria. The LTP should demonstrate that further reductions in residual Identification of survey units having the same area radioactivity necessary to release the site for unre-i classification.
l stricted use (1) would result in net public or environ-Scanning performed to locate small areas of ele-mental harm or (2) were not being made because the re-I I
vated concentrations of residual radioactivity.
sidual levels are as low as reasonably achievable (ALARA)(10 CFR 20.1403(a)). The LTP should also Levels established for m.vestigatmg sigmficantly describe in detail how the requirements of 10 CFR elevated concentrations of residual radioactivity.
l 20.1403(e)(1) or (2) will be met when the restrictions Reference coordinate system established for the fail. If a licensee requests license termination under the site areas.
restricted release criteria of 10 CFR 20.1403, the LTP should document how the public consultation require-l 6.
COMPLIANCE WITH TIIE ments of 10 CFR 20.1403(d) were met.
RADIOLOGICAL CRITERIA FOR LICENSE TERMINATION If a licensee requests license termination under the if a licensee requests unrestricted release of the site alternative radiological criteria in 10 CFR 20.1404, the per Subpart E of 10 CFR Part 20, the LTP should dem-LTP should describe in detail the methods and assump-onstrate that the dose from residual radioactivity that is tions used to demonstrate that public health and safety distinguishable from background radiation does not ex-would continue to be protected. Specifically, the LTP ceed 25 mrem (0.25 mSv) per year to an average mem-should demonstrate that the dose from all man-made ber of the critical group over a 1000-year period, in.
sources combined, other than medical, would be nn-cluding from drinking water. The LTP should also likely to exceed the 100 mrem annual value set forth in demonstrate that residual radioactivity has been re-10 CFR 20.1301(a)(1) and 10 CFR 20.1404(a)(1); that duced to levels that are as low as reasonably achievable the licensee has employed, to the extent practicable, re-(10 CFR 20.1402). The LTP should describe in detail strictions on site use to minimize exposures at the site; j
the methods and assumptions used to demonstrate and that doses have been reduced to ALARA levels, ta-l compliance with the 25-mrem per year criterion. Draft king into consideration any detriments, such as traffic j
Regulatory Guide DG-4006, " Demonstrating Com-accidents, that might result from decontamination or l
pliance With the Radiological Criteria for License Ter-waste disposal. The LTP should discuss site end use, l
mination" (Ref. 4), provides additional interim guid-the institutional controls to be put in place, and the j
ance on how to demonstrate compliance with the maintenance required for the controls (including finan-I unrestricted release, restricted release, and alternative cial assurance for any necessary control and mainte-criteria for license termination. Draft NUREG-1549, nance of the site) until the residual radioactivity meets "Using Decision Methods for Dose Assessment To unrestricted release criteria. If a licensee requests li-Comply With Radiological Criteria for License Te-cense terminatmn under the alternative criteria under mination"(Ref. 9), is being developed to provide in-10 CFR 20.1404, the LTP should document how the 1.179 - 4
public consultation requirements of 10 CFR (Ref.11), provides information on estimating waste 20.1404(a)(4) were met.
disposal costs. No credit for the salvage v ilue of equip-ment should be taken.
/m UPDATE TIIE SITE-SPECIFIC V) 7.
DECOMMISSIONING COSTS 8.
SUPPLEMENT TO TIIE The license termination plan must:
ENVIRONMENTAL REPORT Provide an estimate of the remaining decommis-The licensee must submit a supplement to the envi-sioning costs and
'?nmental report describmg any new m, formation or sigmficant environmental change associated with the Compare the estimated costs with the present funds site-specific termination activities. The supplement to set aside for decommissioning. The financial assu-the environmental report should:
rance instrument required per 10 CFR 50.75 must Deseribe m. detail the impact of the site-specific be funded to the amount of the cost estimate. If there is a deficit in present funding, the LTP must termm, ation activity, indicate the means for ensuring adequate funds to Compare the impact with previously analyzed ter-complete the decommissioning.
mination activities, and Regulatory Guide 1.159," Assuring the Availabil-Analyze the environmental impact of the site-ity of Funds for Decommissioning Nuclear Reactors" specific activity.
(Ref.10), provides detailed guidance on methods for estimating decommissiomng costs, as well as on finan-C. FORMAT OF TIIE LICENSE TERMINATION PLAN GRAPIIIC cial assurance mechanisms that are acceptable to the PRESENTATIONS NRC staff. If the LTP indicates that assurance of fund-ing is to be provided by a surety method, insurance, or Graphic presentations such as drawings, maps, dia-other guarantee, the financial assurance instrument grams, sketches, and tables should be employed if the must remain in effect until the NRC has terminated the information may be presented more adequately or con-license. The decommissioning cost estimate should in-veniently by such means. Due concern should be taken a clude an evaluation of the following cost elements, to ensure that all information so presented is legible, h which are not meant to be all-inclusive, symbols are defined, and that scales are not reduced to Cost assumptions used, including a contingency the extent that visual aids are necessary to interpret per-factor tment items of informatmn. These graphic presenta-tions should appear in the section where they are pri-Major decommissioning activities and tasks marily discussed.
Unit cost factors References may appear either as footnotes to the Estimated costs of decontamination and removal p ge on which they are cited or at the end of each of equipment and structures chapter.
Estimated costs of waste disposal, including appli-PIIYSICAL SPECIFICATIONS a
cable disposal site surcharges Paper Size Estimated final survey costs Text pages: 8-1/2 x 11 inches.
- Estimated total costs Drawings and graphics: 8-1/2 x 11 inches; however, a The cost estimate should focus on the remaining larger size is acceptable provided the finished copy, work, detailed activity by activity, for each activity as-when folded, does not exceed 8-1/2 x 11 inches.
sociated with the decommissioning, including the costs of labor, maten. ls, equipment, energy, and services.
Paper Stock and Ink a
The cost estimates should be based on credible engi-Suitable quality in substance, paper color, and ink den-neering assumptions that are related to all major re-sity for handling and reproduction by microfilming or n'aining decommissioning activities and tasks. The image-copying equipment should be used.
cost estimate should include the cost of the remediation action being evaluated, the cost of transportation and "8
m,
(
) disposal of the waste generated by the action, and other A margin of no less than 1 inch should be maintained on v costs that are appropriate for the specific case.
the top, bottom, and binding side of all pages sub-NUREG-1307, " Report on Waste Burial Charges" mitted.
1.179 - 5
Printing Table of Contents Composition: Text pages should be single-spaced.
A table of contents and an index of key items should be Typeface and Style: Should be suitable for microfilm-ing or image-copying equipment, including computer PROCEDURES FOR UPDATING OR scanning.
REVISING PAGES Reproduction: Mechanically or photographically re-Data and text should be updated or revised by re-produced. All pages of text should be printed on both placing pages. The changed or revised portion on each page should be highlighted by a " change-indicator" sides and the image printed head to head.
mark consisting of a bold verticalline drawn in the mar-Binding: Pages should be punched for standard three-gin opposite the binding margin.The line should be the hole loose-leaf binders.
same length as the portion actually changed.
Page Numbering All p ges submitted to update, revise, or add pages to the report should show the date ofchange and change Pages should be numbered with the digits correspond-or amendment number. A guide page listing the pages ing to the chapter followed by a hyphen and a sequential to be inserted and the pages to be removed should ac-number, e.g., the third page of Section 4 should be num-company the revised pages. When major changes or bered 4-3.The entire report should not be numbered se-additions are made, a revised table of ccmtents should quentially.
be provided.
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1.179 - 6
REFERENCES p 1.
U.S. Nuclear Regulatory Commission,"Decom-6.
USNRC, " Multi-Agency Radiation Survey and
(
missioning of Nuclear Power Reactors"(10 CFR Site Investigation Manual (MARSSIM),"
Parts 2,50, and 51), FederalRegister, Vol. 61, pp.
NUREG-1575, December 1997.2 39278-39304 (61 FR 39278), July 29,1996.
7.
USNRC, " Draft Branch Technical Position on 2.
USNRC, " Decommissioning of Nuclear Power Site Characterization for Decommissioning," No-Reactors," Draft Regulatory Guide DG-1067, vember 1994.3 June 1997.1 8.
A.M. Iluffert, R.A. Meck, and K.M. Miller, 3.
USNRC, " Radiological Criteria for License Ter-
" Background as a Residual Radioactivity Crite-mination"(10 CFR Parts 20,30,40,50,51,70, rion for Decommissioning," USNRC, Draft and 72), Federal Register, Vol. 62, pp.
NUREG-1501, August 1994.1 39058-39092 (62 FR 39058), July 21,1997.
9.
USNRC, " Decision Methods for Dose Assess-4.
USNRC, " Demonstrating Compliance with the ment To Comply With Radiological Criteria for Radiological Criteria for License Termination,"
License Termination" (draft dated March 13 Draft Regulatory Guide DG-4006, August 1998.1 1998, is available as Enclosure 2 to 5.
USNRC, " Standard Format and Content for Post-Shutdown Decommissioning Activities Report,"
- 10. USNRC," Assuring the Availability of Funds for Draft Regulatory Guide DG-1071, December Decommissioning Nuclear Reactors," Regula-1997.1 tory Guide 1.159, August 1990.1
- 11. USNRC, " Report on Waste Burial Charges,"
NUREG-1307, Revision 8, December 1998.2 l
1Single copics of regulatory Fuides, both active and draft, and draft Copies are available at current rates from the U S. Government Print-NUREG reports, may be obtained free of charge by writing the Ing Office, PO. Box 37082, Washington, DC 20402 - 9328 (telephone Office of tSe Chiefinformation Officer, Attn: Printmg, Graphics and (202)512-1800); or from the National Technical lnformation Scr-Distribution Branch. UsNRC, Washington, DC 20555-0001, or by wcc by writmg NTIS at 5285 Port Royal Road, Sprmgfield, \\ A 22161.
fax at (301)415 - 2289 or by email at < DISTRIBUTION Copies are avadaNe for inspection or copying for a fee from the NRC
@ NRC. GOV >. Active guides may also be purchased from the Na-Public Document Room at 2120 L Street NW., Washington, DC; the tional Technical Information Service on a standing order basis. De-PDR's maihng address is Mail Stop LL-6, Washington, DC 20555; tails on this service may be obtained bywriting NTIS.5285 Port Royal telephone (202)634 - 3273; fax (202)634 - 3343.
Road, springfield, VA 22161. Copies of active and draft guides are 3 Copies are available for inspection or copying for a fee from the NRC available for inspection or copymg for a fee from the NRC Public Document Room at 2120 L Street NW., Washington, DC; the PDR's Public Document Room at 2120 L Street NW, Washington, DC; the mailing address is Mail Stop LL-6, Washingtoa, DC 20555; tele-PDR's rnaihng address is Mail Stop LL-6, Washington, DC 20555; phone (202)634-3273; fax (202)634-3343.
telephone (202)634-3273; fax (202)634 -3343.
REGULATORY ANALYSIS A separate regulatory analysis was not prepared for this guide. The regula-tory analysis prepared for the amendments to Parts 2,50, and 51,"Decommis-sioning of Nuclear Power Reactors," which was issued on July 29,1996 (61 FR 39278), provides the regulatory basis for this guide and examines the costs and benefits of the rule as implemented by the guide. A copy of this regulatory analysis is available forinspection or copying for a fee in the NRC Public Doc-ument Room,2120 L Street NW, Washington, D.C.; the PDR's mailing ad-gg dress is Mall Stop LL-6, Washington, D.C. 20555; telephone (202)634-3273;
)
fax (202)634-3343.
v 1.179 - 7
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