ML20205J535
| ML20205J535 | |
| Person / Time | |
|---|---|
| Issue date: | 02/08/1999 |
| From: | Rathbun D NRC OFFICE OF CONGRESSIONAL AFFAIRS (OCA) |
| To: | Gore A, Hastert J, Murphy R GENERAL ACCOUNTING OFFICE, HOUSE OF REP., SPEAKER OF THE HOUSE, SENATE, PRESIDENT OF THE SENATE |
| Shared Package | |
| ML20205J537 | List: |
| References | |
| RTR-REGGD-01.179, RTR-REGGD-1.179 CCS, NUDOCS 9904120076 | |
| Download: ML20205J535 (4) | |
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UNITED STATES s.
j NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. ensam m1 February 8, 1999 The Honorable Al Gore President of the United States Senate Washington, DC 20510
Dear Mr. President:
Pursuant to Subtitle E of the Small Business Regulatory Enforcement Fairness Act of 1096, 5 U.S.C. 801 et seq., the Nuclear Regulatory Commission (NRC) is submitting a finai " rule" as defined in 5 U.S.C. 804. It is Regulatory Guide 1.179, " Standard Format and Content of License Termination Plans for Nuclear Power Reactors." This regulatory guide provides guidance on developing License Termination Plans for nuclear power reactor licensees who wish to terminate their licenses and release their sites.
We have determined that this regulatory guide is not a " major rule" as defined in 5 U.S.C.
804(2), and we have confirmed this determination with the Office of Management and Budget.
Enclosed is a copy of Regulatory Guide 1.179, which is scheduled to be issued in January 1999.
Sincerely, f
Dennis K. Rathbun, Director Office of Congressional Affairs
Enclosure:
Regulatory Guide 1.179 Cgg 9904120076 990208
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!L UNITED STATES p
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20656-0001 t
l The Honorable J. Dennis Hastert Speaker of the United States House of Representatives l
Washington, DC 20515
Dear Mr. Speaker:
Pursuant to Subtitle E of the Small Business Regulatory Enforcement Fairness Act of 1996, 5 U.S.C. 801 et seq., the Nuclear Regulatory Commission (NRC) is submitting a final " rule" as defined in 5 U.S.C. 804. It is Regulatory Guide 1.179, " Standard Format and Content of License Termination Plans for Nuclear Power Reactors." This regulatory guide provides guidance on developing License Termination Plans for nuclear power reactor licensees who
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wish to terminate their licenses and release their sites.
We have determined thrt this regulatory guide is not a " major rule" as defined in 5 U.S.C.
804(2), and we have confirmed this determination with the Office of Management and Budget.
Enclosed is a copy of Regulatory Guide 1.179, which is scheduled to be issued in January 1999.
Sincerely, M
)
Dennis K. Rathbun, Director Office of Congressional Affairs 1
Enclosure:
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g UNITED STATES s
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON D.C. 20066 4001 s,,,
February 8, 1999 j
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Mr. Robert P. Murphy General Counsel General Accounting Office Room 7175 441 G St., NW.
Washington, DC 20548
Dear Mr,
Murphy:
i Pursuant to Subtitle E of the Small Business Regulatory Enforcement Fairness Act of 1996, 5 U.S.C. 801 et seq., the Nuclear Regulatory Commission (NRC) is submitting a final " rule" as defined in 5 U.S.C. 804. It is Regulatory Guide 1.179, " Standard Format and Content of License Termination Plans for Nuclear Power Reactors." This regulatory guide provides guidarsce on developing License Termination Plans for nuclear power reactor licensees who wish to terminate their licenses and release their sites.
We have determined that this regulatory guide is not a " major rule" as defined in 5 U.S.C.
804(2), and we have confirmed this determination with the Office of Management and Budget.
Enclosed is a copy of Regulatory Guide 1.179, which is scheduled to be issued in January 1999.
Sincerely,
/
ME r
~-
Dennis K. Rathbun, Director Office of Congressional Affairs
Enclosure:
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REGULATORY GU DE U.S. NUCLEAR REGULATORY COMMISSION January 1999 O
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OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 1.179 (Draft was issued as DG-1078) i STANDARD FORMAT AND CONTENT OF LICENSE TERMINATION PLANS FOR NUCLEAR POWER REACTORS e
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 prescribe specific public meeting must be held near the site; any hearing n criteria for decommissioning nuclear power reactors; held in relation to the LTP would fall under either Sub-(j they were effective August 28,1996.This rule,by elim-part G or Subpart L of Part 2. If the fuel has been perma-inating, revising, or extending operating reactor requi-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 certain changes that do not result in an unreviewed (2) major decommissioning and storage activities, and safety questmn or changes to the tecur.: cal specifica-(3) license termination activities. Draft Regulatory tions, and the changes must meet the requirements of j
Guide DG-1067, " Decommissioning of Nuclear 10 CFR 50.82(a)(6).
Power Reactors" (Ref. 2), is being developed to de-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-U5NRC R1 GULATORY GUIDIS The gwdes are issued m the toltownng ten broad divisons Regulatory Guides are inaued to desenbe and make available to the public such informa-tion as methods acceptable to the NRC staff forimplementing specific parts of the Com-1 Power oesctors 6 Products trusson's regulat.ons techniques used by the staff inavstunting specific problems or poo 2 Research and Test Fleactors 7 Transportation tulated accsoems. and data needed by the NRC staff in na review of applications for per.
3 Fueis ena Matenals Facsisties 8 Occentional Health wrth n is qui at and sol ons ro tr t
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Fa otection 1
Ge al wdl be acceptable if they provide a bens for the ti engs requiste to the issuance or con.
bnuance of a pomut or license by the Comfrusuon Single copies of regulatory guides may be obtained trea of charge t,y wntng the Fiepro-a n
n eo e a n S
eg T as gedo was issued after conaderation of comments received from the public Com, p
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monts and 5;30sstions for improvements in these guides are encouraged at all times. and or by e mad to GRW1@NRC GOV
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puedes woi be revised, as appropnate. to accommodate comments and to reflect new in-L formhaon or espanence Wntten comments may be submitted to the Ruies and Directives Branch, ADM. U S N#
a stareng order basis Detaas on this service may be obtained Dy wnting NTIS. 52155 Post clear Regulatory Commismon, Westungton. DC 20555-0001.
Royal Road. Spnngfield. VA 22161 h
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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 o'f 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-h#".tification of remaining site dismantlement ac-twitnes cense termination. Draft Regulatory Guide DG-4006, Plans for site remediation
" Demonstrating Compliance With the Radiological Criteria for License 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 relcase, restricted Rthod for demonstrating compliance with the ra-release, and alternative criteria for license termination
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or m-in accordance with Subpart E of 10 CFR Part 20.
stricted release, the LFP should include a desenp-Under the new regulations, in the 1TP a licensee tion of the site's end use, documentation on public 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-ternative criteria For the most part, the LTP will contain a final site characterization, dose assessment, identification of the Updated site-specific estimate of remaining de-remaining remediation activities and supporting plan, commissmmng 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 LTP concurrently with the post-ated with the licensee's proposed termination ac-shutdown decommissioning activities report tivities.
(PSDAR). Guidance is being developed on the content 2.
SITE CIIARACTERIZATION of the PSDAR and is proposed in draft Regulatory Guide DG-1071, " Standard Format and Content fer The purpose of providing information on site 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 licensee can submit the entire site character-oping LTPs for nuclear power reactor licensees who wish to terminate their licenses and release their sites.
iz tion package separately at any time prior to submit-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 determine the extent 3150-0011 and 3150-0021. The NRC may not conduct and range of radiological contamination of structures, or sponsor, and a person is not required to respond to, a systems (including sewer systems, wa3te plumbing collection of information unless it displays a currently systems, Door drains, ventilation ducts, piping and em-valid OMB control number.
bedded piping), rubble, paved parking lots (both on and IL CONTENT OF LICENSE beneath), ground water and surface water, components, TERMINATION PLAN residues, and the environment, including the maximum and average contamination levels and ambient expo-sure rate measurements of all relevant areas (structures, 1.
GENERAL INFORMATION uip.ient, and soils) of the site. The 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 i
The 1 TP should describe l$istoric events (including to the radiation pmtection 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 contammation 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 NRC erite-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 quahty assurance practices used in the 5.
FINAL RADIATION SURVEY PLAN site characterization 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 (MARSSIM)"(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-ical surveys are found at 10 CFR 50.82(a)(9)(ii)(D) and oping a site characterization program, and further gu d-10 CFR 20.1501(a) and (b). The final status survey is ance is bemg developed in NRC's " Draft Branch Tech-the radiation survey performed after an area has been nical Position on Site Characterization for fully characterized, remediation has been completed, Decommissiomng"(Ref. 7 ).
and the licensee believes that the area is ready to be re-
- E"'E ** "
" " " " us survey is to dem-3.
IDENTIFICATION OF REMAINING SITE DISMANTLEMENT ACTIVITIES onstratdiat We area meets the raus. logical criteria for o
license termm, ation. The final status survey is not con-The LTP should contain a discussion of the remain-ducted for the purpose 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. M ARRSIM (Ref. 6) material to be released to unrestricted areas, and the provides guidance on final survey methods and on de-O proposed control mechanisms, person-rem estimates, veloping a final survey plan for demorstrating com-and radioactive waste characterization. The LFP should pliance with Subpart E of 10 CFR Part 20; fuither 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 radiation 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 to identify any inspection or technical resources needed plans, and facility layout drawings should be used l
during the remaining dismantlement activities.
to facilitate presentation), as well as a method for ensuring that sufficient data are included for a The LTP should include a list of the remaining ac-meaningful statistical survey.
tivities that do not mvolve unreviewed safety questions or changes in a facility's technical specifications, and A description of the methods to be used to establish i
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).
A description of the quality assurance (OA) pm-4.
REMEDIATION PLANS Eram to support both field survey work and labora-The LTP should summarize any changes from the tory analysis that addresses the OA organization; i
previously approved radiological control program that training an.d qualification requirements; survey in-will be used for the control of radiological contamina-structions and procedures including water, air, and g
tion associated with the remaining decommissioning soil sampling procedures; document ccmtrol; ccm.
and remediation activities. Details regarding changes trol of purchased items; inspections; c(mtrol of sur-1.179 - 3 l
1 j
vey equipment; handling, storage, and resp <mse terim guidance on an acceptabli: 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 f. licensee requests license termination under the methods to be used for reviewing, analyzing, and restricted release criteria per Subpart.E of 10 CFR auditirg data.
Pan 20 (Ref. 3), the LTP should describe in detail the Verification surveys and evaluations used to sup-rnethods and assumptions that will be used to demon-pod delineation of radiologically affected (con-strate that the licensee will provide reasonable assur-taminated) areas and unaffected (uncontaminated) ance that the dose from residual radioactivity distin-guishable from background will not exceed 25 mrem areas.
per year to a member of the critical group over a Id mtification of the majcr radiological contami-1000-year period with the restrictions in place (10 CFR e
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 nuclides.
in place, and the maintenance required for the controls (including financial assurance for any necessary con-Access contro! medures to control recontamina-trol and maintenance of the site) until the residu:1 radio-tion of clean areas.
activity :n=ts unrestricted releav criteria. The LTP should demonstrate that funher reductions in residual Identification of survey units having the sa-ne area classification.
r dm, activity necessary to release the site for unre-stricted use (1) would result m net public or environ-Scanning performed to locate small areas of ele-mental harm or (2) were not being made because the re-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.vestigatm.g sigmficantly describe m. detail how the requirements of 10 C,FR elevated concentrations of residual radioactivity.
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 arcas.
restricted release criteria of 10 CFR 20.1403, the LTP should document how the public consultation require-6.
COMPLIANCE WITII 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 her of the critical group over a 1000-year period, in-sources combined, other than medical, would be un-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 mimmize exposures at the site; the methods and assumptions used to demonstrate and that doses have been reduced to ALARA levels, ta-cornpliance with the 15-mrem per year criterion. Draft king into consideration any detriments, such as traffic Regulatory Guide DG-4006, " Demonstrating Com-accidents, that might result from decontamination or pliance With the Radiological Criteria for License Ter-waste disposal. The LTP should discuss site end use, mination" (Ref. 4), provides additional interim guid-the institutional controls to he put in place, and the ance on how to demonstrate compliance with the maintenance required for the controls (including finan-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) up 1 ?he residual radioactivity meets j
"Using Decision Methods for Dose Assessment 'Ib unrestricted release enteria. If a licensee requests h-Comply With Radiological Criteria for License Ter-cense termination under the alternative criteria under i
mination"(Ref. 9), is being developed to provide in-10 CFR 20.1404, the LTP should document hov the 1.179 - 4
1 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 value of equip-
'/. UPDATE THE SITE-SPECIFIC DECOMMISSIONING COSTS 8.
SUPPLEMENT TO THE The license termination plan must:
ENVIRONMENTAL REPORT Provide an estimate of the remaining decommis-The licensee must submit a supplement to the envi-j sioning costs and mnmental report describmg any new information 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 be funded to the amount of the cost estimate. If Descrme in detail the impact of the site-specific a
tenmnat, n acdvity, m
there is a deficit in present funding, the ITP must 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.
1 (Ref.10), provides detailed guidance on methods for C. FORMAT OF TiiE LICENSE estimating decommissioning costs, as well as on finan-TERMINATION PLAN GRAPHIC cial assurance mechanisms that are acceptable to the PRESENTATIONS NRC staff. If the LTP indicat's 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 mus' remain in effect until the NRC has terminated the information may be presented more adequately or con-license. The decommissionir.g cost estimate should in-veniently by such means. Due concern should be taken clude an evaluation of the following cost elements, to ensure that all information so presented is legible,
) 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-tinent items of information. These graphic presenta-fu or 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 page on which they are cited or at the end of each of equipment and structures chapter.
Estimated costs of waste disposal, including appli-PHYSICAL SPECIFICATIONS cable disposal site surcharges Paper Size Estimated final survey costs Text pages: 8-1/2 x 11 inches.
Drawings and graphics: 8-1/2 x 11 inches; however, a Fetimated total costs 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 P
St d M M of labor, materials, equipment, energy, and services.
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 j
maining decommissioning activities and tasks. The image-copying equipment should be used.
j cost estimate should include the cost of the remediation 3, age Marg.ms actm.n bem.g evaluated, the cost of transportation and disposal of the waste generated by the actian, and other A margin of no less than 1 inch should be maintained on 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 i
Printing Table of Contents Composition: Text pages should be single-spaced.
A table of contents and an index of key items should be included.
Typeface and Style: Should be suitable for microfilm-ing or image-copying equipment, including computer PROCEDURES FOlt UPDATING Olt scanning.
REVISING PAGES Reproduction: Mechanically or photographically re-Data and text should be updated or revised by re-placing pages. The changed or revised portion on each pro k -d. All pages of text should be printed on both page should be highlighted by a " change-indicator" si&2 ad the image printed head to head.
mark consisting of a bold vertical line drawn in the mar-Binding: Pages should be punched for standard three-gin opposite the binding margin. The line shouid be the hole loose-leaf binders.
same length as the portion actually changed.
Page Numbering All pages 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 contents should quentially, be provided.
O 9
s O
1.179 - 6
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REFERENCES 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),"
s Parts 2,50, and 51), FederalRegisfer, 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. Huffert, 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 Regisfer, 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 SECY-98-051 in the PDR).3 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,"
N'UREG-1307, Revision 8, December 1998.2 O
ISmgle copics of regulatory guides, both active and draft, and draft
<> pics are available at current ratesfrom the U.S. Government Print.
NUREG reports, may be obtamed free of charge by writmg the ing Off ice, PO. Box 37082, Washington. DC 20402 -9328 (telephonc Office of thc Chiefinformation Officer, Attn: Prmting.Graphies and (202)512-1800); or from the National Technical information Scr-Distribution Brandt, USNRC, Washington, DC 20555-0001, or by vice by writing NTIS at 5285 Port Royal Road.Springticid, VA 22161.
fax at (301)415-2289. or by email at < DISTRIBUTION Copics are available for inspection or copying for a fee Irom the NRC
@ NRC. GOV >. Active guides may also be purchased from the Na.
Pubhc Document Room at 2120 L Street NW., Washmgton, DC; the tional Technical Information Service on a standing order basis. De.
PDR s madmg address is Mail Stop LL-6, Washington, DC 20555; tails on this service may be obtained by writing NTIS,5285 Port Royal tclephone (202)634 -3273; fax (202)634-3343.
Road, Springfield. VA 22161. Copies of active and draft guides are 3Copics are available for inspection or copymg for a fee from the NRC available for inspection or copying for a Ice from the NRC Pubhc Puolic Document Room at 2120 L Street NW., Washington, DC; the Document Room at 2120 L Street NW., Washington, DC; the PIRs PDR*s mailmg address is Mail Stop LL-6, Washington, DC 20555; J
maihng address is Mail Stop LL-6, Washington, DC 20555; tele.
telephone (202)634-3273; fax (202)634-3343.
j nhone (202)634-3273; fas (202)634 -3343.
RF.GULATORY 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 is guide and examines the costs l
and benefits of the rule as implemented by the guide. A copy of this regulatory analysis is available for inspection or copying for a fee in the NRC Public Doc-ument Room,2120 L Street NW, Washington, D.C.; the PDR's mailing ad-p dress is Mail Stop LL-6, Washington, D.C. 20555; telephone (202)634-3273; V
fax (202)634-3343.
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M 0
3 M
0 0 I 0
0 S 1
S ION PO S F P
TI E
AR R
GS M
ET I
AC N L D A N
O S
FS G
EEM 4
SA 7
l Pl A
ID l