U.S. NUCLEAR REGULATORY COMMISSION 

REGULATORY

January 1999

GUIDE

OFFICE OF NUCLEAR REGULATORY RESEARCH 

REGULATORY GUIDE 1.179 

(Draft was Issued as DG-1078) 

STANDARD FORMAT AND CONTENT OF LICENSE TERMINATION PLANS 

FOR NUCLEAR POWER REACTORS

A. INTRODUCTION 

On July 29,1996, the NRC published amendments 

to its regulations in 10 CFR Part 2, "Rules of Practice 

for Domestic Licensing Proceedings and Issuance of 

Orders"; 10 CFR Part 50, "Domestic Licensing of Pro

duction and Utilization Facilities"; and 10 CFR Part 51, 

"Environmental Protection Regulations for Domestic 

Licensing and Related Regulatory Functions" (61 FR 

39278) (Ref. 1). These amendments prescribe specific 

criteria for decommissioning nuclear power reactors; 

they were effective August 28,1996. This rule, by elim

inating, revising, or extending operating reactor requi

rements commensurate with their importance to safety, 

specifies requirements for reactors that are permanently 

shut down and have no fuel in the reactor vessel. Reac

tors that are permanently shut down with no fuel in the 

vessel present a significantly reduced risk to the public. 

Decommissioning activities for power reactors 

may be divided into three phases: (1) initial activities, 

(2) major decommissioning and storage activities, and 

(3) license termination activities. Draft Regulatory 

Guide DG-1067, "Decommissioning of Nuclear 

Power Reactors" (Ref. 2), is being developed to de

scribe methods and procedures that are acceptable to 

the NRC staff for implementing the rules that relate to

the initial activities and the major phases of decommis

sioning. 

For Phase 3, 10 CFR 50.82(a)(9) specifies that an 

application for license termination must be accompa

nied or preceded by a license termination plan (LTP), 

which is subject to NRC review and approval. Accord

ing to 10 CFR 50.82(a)(9)(i), the licensee must submit 

an LTP at least two years before termination of the li

cense. The LTP is approved by license amendment. A 

public meeting must be held near the site; any hearing 

held in relation to the LTP would fall under either Sub

part G or Subpart Lof Part 2. If the fuel has been perma

nently removed from the Part 50 facility to an autho

rized facility, a hearing for the proposed LTP would be 

in accordance with Subpart L. Conversely, if an LTP 

were submitted while the spent fuel was stored under 

the Part 50 license, Subpart G of 10 CFR Part 2 would 

apply. 

Even after the LTP has been approved, 10 CFR 

50.59 continues to apply to allow the licensee to make 

certain changes that do not result in an unreviewed 

safety question or changes to the technical specifica

tions, and the changes must meet the requirements of 

10 CFR 50.82(a)(6). 

On July 21, 1997, the Commission amended its 

regulations in 10 CFR Part 20, "Standards for ProtecUSNRC REGULATORY GUIDES The guides are Issued In the following ten broad divisions 

Regulatory Guides are Issued to describe and make available to the public such Informa

tion as methods acceptable to the NRC ataff for Implementing spedfic parts of the Corr, 1. Power Reactors 6. Products 

mission's regulations, techniques used by thestaff inevalueting spedfic problems orpos- 2. Research and Test Reactors 7. "lIteportation 

tulated accidents, and data needed by the NRC staff in Its review of applications for per- 3. Fuels and Materials Fadlities & Occipational Health 

mits and licenses. Regulatory guides we not substitutes for regulations, and compliance 4. Environmental and Siting Q. Antitnrut and Financial Review 

with them Is not required. Methods and solutlons different from thoee set oul In the guides 5. Materials and Plant Protection 10. General 

will be acceptable If they provide a basis for the findings requisite to the Issuance or con

tinuance of a permit or license by t Commission. Single copies of regulatory guides may be obtained free of charge by writing the Repro

This glide was Issued after consideration of comments received from l public. Corn- duction and DistribDtion Services Section, Office of the Chief InformrationOfficer, U.S. Nu

mnsnd 11a and ugge suggestionsfor astIlm onsfridvemerrtsonthfcegentsrencuraged fter thepulic aro Cornd dear Regulatory Commission, Washington, DC20555-0001; or by fax at (301)415-2289; irnrvmp ninthese guldesareencouraged atoall times, end (by e-mall to GRWI @NRC.GYV•. 

des will be revised, as appropriate, to accommodate comnents and to reflect new In

rmation or eIxperence. Issued guides may also be purchased from the National Technical Information Service on 

Written comments may be submitted to the Rules and Directives Branch, ADM, U.S. Nu- a standing order basis. Details onthis service may be obtained by writing NTIS. 5285 Port 

dear Regulatory Commission, Washington. DC 20555-0001. Royal Road, Springfield, VA 22161.
tion Against Radiation"; 10 CFR Part 30, "Rules of 

General Applicability to Domestic Licensing of By

product Material"; 10 CFR Part 40, "Domestic Licens

ing of Source Material"; 10 CFR Parts 50 and 51; 

10 CFR Part 70, "Domestic Licensing of Special Nu

clear Material"; and 10 CFR Part 71, "Packaging and 

Transportation of Radioactive Material" (62 FR 39058, 

Ref. 3), prescribing specific radiological criteria for li

cense termination. Draft Regulatory Guide DG-4006, 

"Demonstrating Compliance With the Radiological 

Criteria for License Termination" (Ref. 4), is being de

veloped to provide additional guidance on demonstrat

ing compliance with the unrestricted release, restricted 

release, and alternative criteria for license termination 

in accordance with Subpart E of 10 CFR Part 20. 

Under the new regulations, in the LTP a licensee 

could propose either release of the facility and site for 

unrestricted use or release of the facility and site under 

restricted use conditions. 

For the most part, the LTP will contain a final site 

characterization, dose assessment, identification of the 

remaining remediation activities and supporting plan, 

and final survey plan. The LTP must be submitted as 

a supplement to the licensee's final safety analysis re

port (FSAR) or as an equivalent document. A licensee 

might submit the LTP concurrently with the post

shutdown decommissioning activities report 

(PSDAR). Guidance is being developed on the content 

of the PSDAR and is proposed in draft Regulatory 

Guide DG-1071, "Standard Format and Content for 

Post-Shutdown Decommissioning Activities Report" 

(Ref. 5). 

This regulatory guide provides guidance on devel

oping LTPs for nuclear power reactor licensees who 

wish to terminate their licenses and release their sites. 

The information collections contained in this regu

latory guide are covered by the requirements of 10 CFR 

Parts 50 and 51, which were approved by the Office of 

Management and Budget, approval numbers 

3150-0011 and 3150-0021. The NRC may not conduct 

or sponsor, and a person is not required to respond to, a 

collection of information unless it displays a currently 

valid OMB control number. 

B. CONTENT OF LICENSE 

TERMINATION PLAN 

1. GENERAL INFORMATION 

The licensee's name, address, license number, and 

docket number should agree with the most recent li

cense. The LTP should address each of the criteria below from 10 CFR 50.82(a)(9), 10 CFR 50.82(a)(10), 

and the related radiological criteria from Subpart E of 

10 CFR Part 20 for unrestricted or restricted release of 

the site. The LTP should include any supporting infor

mation necessary to address the criteria, such as: 

"* Site characterization 

"* Identification of remaining site dismantlement ac

tivities

S 

S

Plans for site remediation 

Detailed plans for the final radiation survey for re

lease of the site

" Method for demonstrating compliance with the ra

diological criteria for license termination. For re

stricted release, the LTP should include a descrip

tion of the site's end use, documentation on public 

consultation, institutional controls, and financial 

assurance needed to comply with the requirements 

for license termination for restricted release or al

ternative criteria 

" Updated site-specific estimate of remaining de

commissioning costs 

" Supplement to the environmental report, pursuant 

to 10 CFR 51.53, that describes any new informa

tion or significant environmental changes associ

ated with the licensee's proposed termination ac

tivities. 

2. SITE CHARACTERIZATION 

The purpose of providing information on site char

acterization is to ensure that final radiation surveys are 

conducted to cover all areas where contamination ex

isted, remains, or has the potential to exist or remain. 

The licensee can submit the entire site character

ization package separately at any time prior to submit

tal of the LTP and reference it in the LTP, or the site 

characterization can be submitted as an integral part of 

the LTR 

The LTP site characterization should be suffi

ciently detailed to allow NRC to determine the extent 

and range of radiological contamination of structures, 

systems (including sewer systems, waste plumbing 

systems, floor drains, ventilation ducts, piping and em

bedded piping), rubble, paved parking lots (both on and 

beneath), ground water and surface water, components, 

residues, and the environment, including the maximum 

and average contamination levels and ambient expo

sure rate measurements of all relevant areas (structures, 

equipment, and soils) of the site. The site characteriza

tion should be sufficiently detailed to provide data for 

planning further decommissioning activities as well as 

the final survey program.

1.179-2
The LTP should describe historic events (including 

dates, types of occurrences, locations in and outside of 

the facility), such as radiological spills, disposals, or 

other radiological accidents or incidents, that resulted 

or could have resulted in contamination of structures, 

equipment, laydown areas, or soils (subfloor and out

side area). 

The LTP should describe the survey instruments 

and supporting quality assurance practices used in the 

site characterization program. The LTP should discuss 

how the data quality objectives discussed in 

NUREG-1575, "Multi-Agency Radiation Survey and 

Site Investigation Manual (MARSSIM)" (Ref. 6), were 

applied during site characterization. 

MARSSIM (Ref. 6) provides guidance on devel

oping a site characterization program, and further guid

ance is being developed in NRC's "Draft Branch Tech

nical Position on Site Characterization for 

Decommissioning'' (Ref. 7). 

3. IDENTIFICATION OF REMAINING SITE 

DISMANTLEMENT ACTVITIES 

The LTP should contain a discussion of the remain

ing tasks associated with the decontamination and dis

mantlement, an estimate of the quantity of radioactive 

material to be released to unrestricted areas, and the 

, proposed control mechanisms, person-rem estimates, 

and radioactive waste characterization. The LTP should 

also identify any decommissioning tasks that require 

coordination with any other Federal or State regulatory 

agency. 

In the LTP, the areas and equipment that need fur

ther remediation should be described in sufficient detail 

to allow the reviewer to prdict the radiological condi

tions that will be encountered during remediation. The 

details in this section should be sufficient for the NRC 

to identify any inspection or technical resources needed 

during the remaining dismantlement activities. 

The LTP should include a list of the remaining ac

tivities that do not involve unreviewed safety questions 

or changes in a facility's technical specifications, and 

this list should be sufficiently detailed for the staff to 

confirm that remedial activities may in fact be carried 

out under 10 CFR 50.59. 

4. REMEDIATION PLANS 

The LTP should summarize any changes from the 

previously approved radiological control program that 

will be used for the control of radiological contamina

tion associated with the remaining decommissioning 

and remediation activities. Details regarding changes

to the radiation protection program are not required in 

the LTP, but would be included in periodic updates to 

the Final Safety Analysis Report. 

The LTP should discuss in detail the remediation 

methods and techniques that will be used to demon

strate that the facility and site areas meet the NRC crite

ria for license termination in Subpart E of 10 CFR Part 

20 (Ref. 3). 

5. FINAL RADIATION SURVEY PLAN 

The LTP should describe the final survey plan for 

confirming that the plant and site will meet the re

stricted or unrestricted release criteria in Subpart E of 

10 CFR Part 20 (Ref. 3) for license termination, as ap

plicable. The NRC's regulations applicable to radiolog

ical surveys are found at 10 CFR 50.82(a)(9)(ii)(D) and 

10 CFR 20.1501(a) and (b). The final status survey is 

the radiation survey performed after an area has been 

fully characterized, remediation has been completed, 

and the licensee believes that the area is ready to be re

leased. The purpose of the final status survey is to dem

onstrate that the area meets the radiological criteria for 

license termination. The final status survey is not con

ducted for the purpose of locating residual radioactiv

ity; the historical site assessment and the characteriza

tion survey perform that function. MARRSIM (Ref. 6) 

provides guidance on final survey methods and on de

veloping a final survey plan for demonstrating com

pliance with Subpart E of 10 CFR Part 20; further guid

ance is proposed in Regulatory Position 2 of Draft 

Regulatory Guide DG-4006, "Demonstrating Com

pliance with the Radiological Criteria for License Ter

mination" (Ref. 4). The following items, which are not 

meant to be all-inclusive, should be included in the fi

nal radiation survey plan. 

"* The methods proposed for surveying all equip

ment, systems, structures, and soils (diagrams, plot 

plans, and facility layout drawings should be used 

to facilitate presentation), as well as a method for 

ensuring that sufficient data are included for a 

meaningful statistical survey. 

"* A description of the methods to be used to establish 

background radiation levels (variances in back

ground radiation can be expected between struc

tures constructed of different materials) (Ref. 8). 

"* A description of the quality assurance (QA) pro

gram to support both field survey work and labora

tory analysis that addresses the QA organization; 

training and qualification requirements; survey in

structions and procedures including water, air, and 

soil sampling procedures; document control; con

trol of purchased items; inspections; control of sur1.179-3
vey equipment; handling, storage, and response 

checks; shipping of survey equipment and labora

tory samples; nonconformance items; corrective 

action; QA records; and survey audits, including 

methods to be used for reviewing, analyzing, and 

auditing data. 

" Verification surveys and evaluations used to sup

port delineation of radiologically affected (con

taminated) areas and unaffected (uncontaminated) 

areas. 

" Identification of the major radiological contami

nants. 

" Methods used for addressing hard-to-detect radio

nuclides. 

" Access control procedures to control recontamina

tion of clean areas. 

* Identification of survey units having the same area 

classification. 

Scanning performed to locate small areas of ele

vated concentrations of residual radioactivity. 

Levels established for investigating significantly 

elevated concentrations of residual radioactivity. 

Reference coordinate system established for the 

site areas. 

6. COMPLIANCE WITH THE 

RADIOLOGICAL CRITERIA FOR 

LICENSE TERMINATION 

If a licensee requests unrestricted release of the site 

per Subpart E of 10 CFR Part 20, the LTP should dem

onstrate that the dose from residual radioactivity that is 

distinguishable from background radiation does not ex

ceed 25 mrem (0.25 mSv) per year to an average mem

ber of the critical group over a 1000-year period, in

cluding from drinking water. The LTP should also 

demonstrate that residual radioactivity has been re

duced to levels that are as low as reasonably achievable 

(10 CFR 20.1402). The LTP should describe in detail 

the methods and assumptions used to demonstrate 

compliance with the 25-mrem per year criterion. Draft 

Regulatory Guide DG-4006, "Demonstrating Com

pliance With the Radiological Criteria for License Ter

mination" (Ref. 4), provides additional interim guid

ance on how to demonstrate compliance with the 

unrestricted release, restricted release, and alternative 

criteria for license termination. Draft NUREG-1549, 

"Using Decision Methods for Dose Assessment To 

Comply With Radiological Criteria for License Ter

mination" (Ref. 9), is being developed to provide interim guidance on an acceptable methodology for cal

culating dose. 

If a licensee requests license termination under the 

restricted release criteria per Subpart E of 10 CFR 

Part 20 (Ref. 3), the LTP should describe in detail the 

methods and assumptions that will be used to demon

strate that the licensee will provide reasonable assur

ance that the dose from residual radioactivity distin

guishable from background will not exceed 25 mrem 

per year to a member of the critical group over a 

1000-year period with the restrictions in place (10 CFR 

20.1401(d) and 10 CFR 20.1403(b)). The LTP should 

discuss site end use, the institutional controls to be put 

in place, and the maintenance required for the controls 

(including financial assurance for any necessary con

trol and maintenance of the site) until the residual radio

activity meets unrestricted release criteria. The LTP 

should demonstrate that further reductions in residual 

radioactivity necessary to release the site for unre

stricted use (1) would result in net public or environ

mental harm or (2) were not being made because the re

sidual levels are as low as reasonably achievable 

(ALARA) (10 CFR 20.1403(a)). The LTP should also 

describe in detail how the requirements of 10 CFR 

20.1403(e)(1) or (2) will be met when the restrictions 

fail. If a licensee requests license termination under the 

restricted release criteria of 10 CFR 20.1403, the LTP 

should document how the public consultation require

ments of 10 CFR 20.1403(d) were met. 

If a licensee requests license termination under the 

alternative radiological criteria in 10 CFR 20.1404, the 

LTP should describe in detail the methods and assump

tions used to demonstrate that public health and safety 

would continue to be protected. Specifically, the LTP 

should demonstrate that the dose from all man-made 

sources combined, other than medical, would be un

likely to exceed the 100 mrem annual value set forth in 

10 CFR 20.1301(aXl) and 10 CFR 20.1404(aXl); that 

the licensee has employed, to the extent practicable, re

strictions on site use to minimize exposures at the site; 

and that doses have been reduced to ALARA levels, ta

king into consideration any detriments, such as traffic 

accidents, that might result from decontamination or 

waste disposal. The LTP should discuss site end use, 

the institutional controls to be put in place, and the 

maintenance required for the controls (including finan

cial assurance for any necessary control and mainte

nance of the site) until the residual radioactivity meets 

unrestricted release criteria. If a licensee requests li

cense termination under the alternative criteria under 

10 CFR 20.1404, the LTP should document how the

1.179-4

K
public consultation requirements of 10 CFR 

20.1404(a)(4) were met. 

7. UPDATE THE SITE-SPECIFIC 

DECOMMISSIONING COSTS 

The license termination plan must: 

* Provide an estimate of the remaining decommis

sioning costs and 

• Compare the estimated costs with the present funds 

set aside for decommissioning. The financial assu

rance instrument required per 10 CFR 50.75 must 

be funded to the amount of the cost estimate. If 

there is a deficit in present funding, the LTP must 

indicate the means for ensuring adequate funds to 

complete the decommissioning. 

Regulatory Guide 1.159, "Assuring the Availabil

ity of Funds for Decommissioning Nuclear Reactors" 

(Ref. 10), provides detailed guidance on methods for 

estimating decommissioning costs, as well as on finan

cial assurance mechanisms that are acceptable to the 

NRC staff. If the LTP indicates that assurance of fund

ing is to be provided by a surety method, insurance, or 

other guarantee, the financial assurance instrument 

must remain in effect until the NRC has terminated the 

license. The decommissioning cost estimate should in

clude an evaluation of the following cost elements, 

which are not meant to be all-inclusive. 

"• Cost assumptions used, including a contingency 

factor 

"* Major decommissioning activities and tasks 

"* Unit cost factors 

"* Estimated costs of decontamination and removal 

of equipment and structures 

• Estimated costs of waste disposal, including appli

cable disposal site surcharges 

* Estimated final survey costs 

* Estimated total costs 

The cost estimate should focus on the remaining 

work, detailed activity by activity, for each activity as

sociated with the decommissioning, including the costs 

of labor, materials, equipment, energy, and services. 

The cost estimates should be based on credible engi

neering assumptions that are related to all major re

maining decommissioning activities and tasks. The 

cost estimate should include the cost of the remediation 

action being evaluated, the cost of transportation and 

disposal of the waste generated by the action, and other 

costs that are appropriate for the specific case. 

NUREG-1307, "Report on Waste Burial Charges"

(Ref. 11), provides information on estimating waste 

disposal costs. No credit for the salvage value of equip

ment should be taken. 

8. SUPPLEMENT TO THE 

ENVIRONMENTAL REPORT 

The licensee must submit a supplement to the envi

ronmental report describing any new information or 

significant environmental change associated with the 

site-specific termination activities. The supplement to 

the environmental report should: 

"* Describe in detail the impact of the site-specific 

termination activity, 

"* Compare the impact with previously analyzed ter

mination activities, and 

"* Analyze the environmental impact of the site

specific activity. 

C. FORMAT OF THE LICENSE 

TERMINATION PLAN GRAPHIC 

PRESENTATIONS 

Graphic presentations such as drawings, maps, dia

grams, sketches, and tables should be employed if the 

information may be presented more adequately or con

veniently by such means. Due concern should be taken 

to ensure that all information so presented is legible, 

symbols are defined, and that scales are not reduced to 

the extent that visual aids are necessary to interpret per

tinent items of information. These graphic presenta

tions should appear in the section where they are pri

marily discussed. 

References may appear either as footnotes to the 

page on which they are cited or at the end of each 

chapter. 

PHYSICAL SPECIFICATIONS 

Paper Size 

Text pages: 8-1/2 x 11 inches. 

Drawings and graphics: 8-1/2 x 11 inches; however, a 

larger size is acceptable provided the finished copy, 

when folded, does not exceed 8-1/2 x 11 inches. 

Paper Stock and Ink 

Suitable quality in substance, paper color, and ink den

sity for handling and reproduction by microfilming or 

image-copying equipment should be used. 

Page Margins 

A margin of no less than 1 inch should be maintained on 

the top, bottom, and binding side of all pages sub

mitted.

1.179-5
Printing 

Composition: Text pages should be single-spaced. 

Typeface and Style: Should be suitable for microfilm

ing or image-copying equipment, including computer 

scanning. 

Reproduction: Mechanically or photographically re

produced. All pages of text should be printed on both 

sides and the image printed head to head. 

Binding: Pages should be punched for standard three

hole loose-leaf binders. 

Page Numbering 

Pages should be numbered with the digits correspond

ing to the chapter followed by a hyphen and a sequential 

number, e.g., the third page of Section 4 should be num

bered 4-3. The entire report should not be numbered se

quentially.

Table of Contents

A table of contents and an index of key items should be 

included. 

PROCEDURES FOR UPDATING OR 

REVISING PAGES 

Data and text should be updated or revised by re

placing pages. The changed or revised portion on each 

page should be highlighted by a "change-indicator" 

mark consisting of a bold vertical line drawn in the mar

gin opposite the binding margin. The line should be the 

same length as the portion actually changed. 

All pages submitted to update, revise, or add pages 

to the report should show the date of change and change 

or amendment number. A guide page listing the pages 

to be inserted and the pages to be removed should ac

company the revised pages. When major changes or 

additions are made, a revised table of contents should 

be provided.

1.179-6
REFERENCES

1. U.S. Nuclear Regulatory Commission, "Decom

ly missioning of Nuclear Power Reactors" (10 CFR 

Parts 2,50, and 51), FederalRegister, Vol. 61, pp. 

39278-39304 (61 FR 39278), July 29, 1996. 

2. USNRC, "Decommissioning of Nuclear Power 

Reactors," Draft Regulatory Guide DG-1067, 

June 1997.1 

3. USNRC, "Radiological Criteria for License Ter

mination" (10 CFR Parts 20, 30, 40, 50, 51, 70, 

and 72), Federal Register, Vol. 62, pp. 

39058-39092 (62 FR 39058), July 21, 1997. 

4. USNRC, "Demonstrating Compliance with the 

Radiological Criteria for License Termination," 

Draft Regulatory Guide DG-4006, August 1998.1 

5. USNRC, "Standard Format and Content for Post

Shutdown Decommissioning Activities Report," 

Draft Regulatory Guide DG-1071, December 

1997.1 

" 1

Single copies of regulatory guides, both active and draft, and draft 

NUREG reports, may be obtained free of charge by writing the 

Office of the Chief Information Officer, Attn: Printing, Graphics and 

Distribution Branch, USNRC, Washington, DC 20555-0001, or by 

fax at (301)415-2289, or by email at <DISTRIBUTION 

@NRC.GOV>. Active guides may also be purchased from the Na

tional Technical Information Service on a standing order basis. De

tails on this service may be obtained bywriting NTIS, 5285 Port Royal 

Road, Springfield, VA 22161. Copies of active and draft guides are available for inspection or copying for a fee from the NRC Public 

Document Room at 2120 L Street NW, Washington, DC; the PDR's 

mailing address is Mail Stop LL-6, Washington, DC 20555; tele

phone (202)634-3273; fax (202)634-3343.

6. USNRC, "Multi-Agency Radiation Survey and 

Site Investigation Manual (MARSSIM)," 

NUREG-1575, December 1997.2 

7. USNRC, "Draft Branch Technical Position on 

Site Characterization for Decommissioning," No

vember 1994.3 

8. A.M. Huffert, R.A. Meck, and K.M. Miller, 

"Background as a Residual Radioactivity Crite

rion for Decommissioning," USNRC, Draft 

NUREG-1501, August 1994.1 

9. USNRC, "Decision Methods for Dose Assess

ment To Comply With Radiological Criteria for 

License Termination" (draft dated March 13, 

1998, is available as Enclosure 2 to 

SECY-98-051 in the PDR).3 

10. USNRC, "Assuring the Availability of Funds for 

Decommissioning Nuclear Reactors," Regula

tory Guide 1.159, August 1990.1 

11. USNRC, "Report on Waste Burial Charges," 

NUREG-1307, Revision 8, December 1998.2 

2

Copies are available at current rates from the US. Government Print

ing Office, P.O. Box 37082, Washington, DC 20402 - 9328 (telephone 

(202)512-1800); or from the National Technical Information Ser

vice by writing NTIS at 5285 Port Royal Road, Springfield, VA22161. 

Copies are available for inspection or copying for a fee from the NRC 

Public Document Room at 2120 L Street NW., Washington, DC; the 

PDR's mailing address is Mail Stop LL-6, Washington, DC 20555; 

telephone (202)634-3273; fax (202)634-3343. 3Copies are available for inspection or copying for a fee from the NRC 

Public Document Room at 2120 L Street NW., Washington, DC; the 

PDR's mailing address is Mail Stop LL-6, Washington, DC 20555; 

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 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

dress is Mail Stop LL-6, Washington, D.C. 20555; telephone (202)634-3273; 

fax (202)634-3343.

1.179-7

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