Issue Date: 11/12/96 - 1 - 2605

NRC INSPECTION MANUAL NMSS

MANUAL CHAPTER 2605

DECOMMISSIONING PROCEDURES FOR

FUEL CYCLE AND MATERIALS LICENSEES

2605-01 PURPOSE

To establish policies and procedures for decommissioning fuel

cycle and materials licensees. 

2605-02 OBJECTIVES

02.01 To establish and compile general policies for the

decommissioning of fuel cycle and materials sites.

02.02 To establish general procedures for the regulatory

oversight of decommissioning of fuel cycle and materials sites.

02.03 To aid in the achievement of consistent actions by the

staff involved in the decommissioning of fuel cycle and

materials sites.

To meet these objectives, and assist individuals involved in

decommissioning nuclear facilities, the Nuclear Regulatory

Commission staff has developed the Office of Nuclear Material

Safety and Safeguards (NMSS) Decommissioning Handbook which

summarizes the regulations, policies, and procedures that shall

be used by NRC staff during the decommissioning of nuclear fuel

cycle and materials facilities subject to the Commission's

jurisdiction. This manual chapter summarizes the basic

framework for decommissioning these facilities, and directs the

staff to the appropriate sections of the Decommissioning

Handbook for specific information on the procedures to be

followed by NRC staff overseeing NRC's decommissioning program

at these facilities.

2605-03 DEFINITIONS

03.01 ALARA. (acronym for As Low as is Reasonably

Achievable) means making every reasonable effort to maintain

exposures to radiation as far below NRC's dose limits as is

practical taking into account the state of technology, the

economics of improvements in relation to the state of

technology, the economics of improvements in relation to

benefits to the public health and safety, and other societal
2605 - 2 - Issue Date: 11/12/96

and socioeconomic considerations, and in relation to

utilization of licensed material in the public interest.

03.02 Categorical Exclusion. A category of actions which do

not individually or cumulatively have a significant impact on

the human 
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environment and which the Commission has found to have no such

effect in accordance with the procedures set out in 10 CFR

51.22.

03.03 Closeout Inspection. An inspection performed by NRC to

determine if a licensee has adequately decommissioned its

facility. Typically, closeout inspections are performed after

licensees have demonstrated that its facility is suitable for

release in accordance with NRC requirements.

03.04 Confirmatory Survey. A survey conducted by the NRC (or

an NRC contractor) to verify the results of the licensee's

Closeout Survey. Typically Confirmatory surveys consist of

measurements at a small percentage of locations previously

surveyed by the licensee to determine whether the licensee's

results are valid and reproducible.

03.05 Decommission. To remove a facility safely from service

and reduce residual radioactivity to a level that permits

release of the property and termination of the license.

03.06 Decommissioning Plan (DP). A detailed description of

the activities the licensee, or responsible party, intends to

use to assess the radiological status of its facility; to

remove radioactivity attributable to licensed operations at its

facility to levels that permit release of the site in

accordance with NRC's regulations and termination of the

license; and to demonstrate that the facility meets NRC's

requirements for release. A DP typically consists of several

interrelated components, including: site characterization

information; a remediation plan (which itself includes several

components including a description of remediation tasks, a

health and safety plan, and a quality assurance plan); sitespecific cost estimates for the decommissioning; and a final

status survey plan. 

03.07 Environmental Assessment (EA). A concise public

document that serves to:

1. Briefly provide sufficient evidence and analysis for

determining whether to prepare an Environmental Impact

Statement (EIS) or Finding of No Significant Impact

(FONSI).

2. Aid NRC's compliance with the National Environmental

Policy Act (NEPA) when no EIS is necessary.

3. Facilitate preparation of an EIS when one is necessary.

03.08 Environmental Impact Statement (EIS). A detailed

written statement as required by section 102(2)(C) of NEPA.

03.09 Environmental Report (ER). A report developed by a

licensee that is submitted to support the licensee's amendment

request. The ER is used by NRC staff to prepare EAs and EISs.

The requirements for ERs are specified in 10 CFR 51.45 - 51.69.
2605 - 4 - Issue Date: 11/12/96

03.10 Final Status Survey (FSS) . A survey conducted by a

licensee to demonstrate the radiological status of its

facility. Typically, closeout surveys consist of evaluations

for both fixed and removable residual radioactive material, and

determinations of radiation levels in formerly used areas.

Also referred to as a Closeout Survey, or Termination Survey.

03.11 Finding of No Significant Impact (FONSI) . A concise

public document that briefly states the reasons why an action

will not have a significant impact on the human environment.

03.12 Safety Evaluation Report (SER). The NRC staff's

evaluation of a licensee's proposed action to determine if the

proposed action can be accomplished safely.

03.13 Suitable for Unrestricted Use. A site at which the

level of residual radioactivity distinguishable from background

is sufficiently low so as to allow any public use of the site

without restrictions.

2605-04 RESPONSIBILITIES AND AUTHORITIES

04.01 All NRC personnel implementing the decommissioning

program for fuel cycle and materials facilities shall use the

guidance identified in this manual chapter and the NMSS

Decommissioning Handbook. This manual chapter and

Decommissioning Handbook shall also be used by NRC personnel

implementing the decommissioning program at: formerly licensed

sites for which the licenses were previously terminated; sites

involving source, special nuclear, or byproduct material

subject to NRC regulation for which a license was never issued;

and sites in NRC's Site Decommissioning Management Plan (SDMP)

program (see below). Significant deviations from this guidance

shall be employed only after review and approval by the

appropriate NRC management. 

NRC personnel implementing the decommissioning program for

nuclear reactor facilities subject to regulation under 10 CFR

Part 50 are not required to use the guidance identified in this

manual chapter. NRC staff implementing the decommissioning

program at uranium recovery facilities shall use the guidance

in Manual Chapter 2801, "11e.(2) Byproduct Material Disposal

Site and Facility Inspection Program."

04.02 Except as discussed above, this decommissioning program

applies to all NRC licensees under 10 CFR Parts 30, 40, 70, and

72 undergoing decommissioning. The principal regulations

governing decommissioning are: 10 CFR 30.4, 30.32, 30.35,

30.36, 40.4, 40.31, 40.36, 40.42, 70.4, 70.22, 70.25, 70.38,

72.3, 72.30, and 72.54. 

04.03 The responsibility for implementing the decommissioning

program at nuclear facilities resides with the NRC regional

office in which the facility is located, or NMSS, as

appropriate. The lead office has the responsibility for

coordinating the implementation of the decommissioning program
 1

The effective date of the final rule on timeliness in decommissioning

was August 15, 1994 (59 FR 36026, July 15, 1994). Licensees with unused

facilities on August 15, 1994, are required to submit the required

notifications to NRC by October 15, 1996. Within 12 months of submitting the

notification, these licensees are required to submit a decommissioning plan (if

required) and begin decommissioning their facilities upon approval of the plan

by NRC. Unless otherwise approved by NRC, licensees are required to complete

decommissioning their facilities within 24 months of initiating decommissioning

operations. Licensees that have made decommissioning notifications prior to

August 15, 1994 do not need to provide another notification. However, these

licensees were required to submit a decommissioning plan, or request an

alternative decommissioning schedule, by August 15, 1995.

 2On August 22, 1994, (see 59 FR 43200) NRC announced its intention to

amend its regulations to establish radiological criteria for decommissioning. 

As discussed in this announcement, NRC may consider decommissioning actions

that would result in restricted use of the facility following decommissioning. 

Until criteria for decommissioning nuclear facilities are finalized the staff

should use the interim radiological criteria identified in the SDMP Action Plan

(57 FR 13389).

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at the facility within NRC. In general, the regional office

will assume lead responsibility for most licensed sites

undergoing decom-missioning. NMSS will provide overall program

and policy direction for the regional offices for

decommissioning facilities. NMSS will also provide oversight

guidance and site-specific support to the regions for all

decommissioning facilities to ensure that licensees are

conducting the decommissioning in a consistent manner. NMSS

may assume oversight responsibility for sites listed on the

SDMP, or others, after consultation with the regional office.

Staff should refer to Section 1 of the NMSS Decommissioning

Handbook for the procedures to be followed to determine the

appropriate lead office for decommissioning nuclear facilities.

2605-05 GENERAL GUIDANCE

05.01 Timing of Decommissioning. NRC regulations at 10 CFR

30.36(d)(1-4), 40.42(d)(1-4), 70.38(d)(1-4), and 72.54(d)(1-3)1

describe the conditions under which a licensed facility would

be required to commence decommissioning operations. 

In March 1990, NRC established the SDMP to help ensure the

timely cleanup of sites warranting special attention by the

Commission. As summarized in the SDMP Action Plan (57 FR

13389), NRC staff shall address the timing of SDMP site

cleanups on a case-by-case basis, with the expectation the

cleanup will be completed in about 4 years after operations

that caused the contamination cease, or 3 years after issuance

of an initial cleanup order. 

Section 3 of the NMSS Decommissioning Handbook discusses the

conditions under which licensed nuclear facilities, as well as

SDMP sites, are required to commence decommissioning

operations. 

05.02 Radiological Criteria for Decommissioning2

. Generally,

licensees decommission their facilities with the intent of
2605 - 6 - Issue Date: 11/12/96

terminating the license and using the facility for activities

that do not involve licensed material. These facilities must

be decommissioned such that they do not contain residual

radioactive material levels in excess of NRC's criteria for

unrestricted use. Section 4 of the NMSS Decommissioning

Handbook summarizes NRC's interim radiological criteria for

unrestricted use. 

05.03 Decommissioning Records Management. SECY-90-316,

"Decommissioning Records Plan (DRP)" and Records Management

Guideline (RMG) 92-01, "Plan for Decommissioning Records,"

describe the records management and retention requirements for

the decommissioning of licensed nuclear facilities. In

general, the RMG requires that all records associated with

decommissioning nuclear facilities be maintained for 20 years.

Records that are determined to have significant historical

value will be permanently retained. RMG 93-03, "Final Criteria

for Determining That Records Should be Retained Permanently

Because of Significant Historical Value," describes the

criteria for determining which records have significant

historical value and should be permanently retained. The

Office of Information Resources Management has been assigned

lead responsibility for implementing the requirements of the

DRP. In addition, on May 16, 1996, NRC amended its regulations

pertaining to the disposition of certain records when a

licensee terminates licensed activities or licensed activities

are transferred to another licensee (61 FR 24669). The rule

requires that licensees transfer records pertaining to

decommissioning, and certain records pertaining to off-site

releases and waste disposal, to the new licensee if licensed

activities will continue at the same site, and it requires that

the new licensee forward these same records to NRC before the

license is terminated. SECY-90-316, RMG 92-01, RMG 93-03, and

NRC's decommissioning recordkeeping requirements are discussed

in Section 5 of the NMSS Decommissioning Handbook. 

05.04 The National Environmental Policy Act of 1969. 10 CFR

Parts 2 and 51 describe the activities required for compliance

with the Administrative Procedure Act (APA) and NEPA. 10 CFR

Part 2 describes the procedures for the issuance, amending,

transfer, or renewal of a license, including notifying State

and local officials and the public of the NRC staff's actions,

or intended actions, the public's involvement in the licensing

process and the conduct of hearings related to licensing

actions. 10 CFR Part 51 describes the procedures and

requirements for evaluating licensees' proposed actions under

NEPA including the development of EAs and EIS' and the

requirement to notice these actions and solicit input from

interested members of the public. NRC staff should refer to

Section 13 of the NMSS Decommissioning Handbook for information

on the appropriate procedures to be followed to comply with

NEPA.

2605-06 SPECIFIC GUIDANCE 
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06.01 Decommissioning Types. Generally, the staff will

evaluate the decommissioning of nuclear facilities using one of

four reviews (referred to as "Types"), as discussed below. NRC

staff should refer to Section 7 of the Decommissioning Handbook

to determine the appropriate decommissioning type for their

site, as well as the actions that should be taken by NRC staff

upon notification of a licensee's intent to decommission its

facility. 

Although it is anticipated that most licensees will fall under

the decommissioning types as outlined, it should be expected

that the actions may not always be appropriate for each

licensee. The intent is to present the generally appropriate

actions to be taken by NRC staff, recognizing that the unique

nature of some facilities may require site-specific

modifications to the procedures. The staff shall ensure that

any departure from these established procedures is reviewed and

approved by NRC management and documented in writing prior to

their implementation. 

a. Type I Review

In general, facilities decommissioned under Type I only have

used licensed material in a manner that would preclude its

release into the environment, would not cause the activation

of adjacent materials, or the contamination of work areas.

Typically, facilities decommissioned under Type I would be

limited to licensees that: 

1. Possess and use only sealed sources and the most

recent leak test demonstrates that the source(s)

did not leak while in the licensee's possession;

or 

2. Possess and use relatively short-lived radioactive

material (i.e., T1/2 < 60 days) in unsealed forms

and the maximum activities authorized under the

license have decayed to less than the quantities

specified in 10 CFR Part 20, Appendix C. 

Any significant leakage of the sealed source or sources

(i.e., >0.005 μCi), or if the activity of the radioactive

material is in excess of the limits outlined in 10 CFR Part

20, Appendix C would require decommissioning under Type II or

Type III decommissioning, described below. 

Type I decommissioning would not require the licensee to

develop a DP, or to perform a FSS. However, the licensee

would be required to submit a completed NRC Form 314, or

equivalent, and demonstrate that its facility was suitable

for unrestricted use. This could be accomplished by the

licensee demonstrating that it met either condition discussed

above, or by performing an adequate FSS. NRC staff would

evaluate the information submitted by the licensee, but would

not perform either a closeout inspection or confirmatory

survey at the licensee's facility.
 3

Licensees using small quantities of 14C or 3

H may be decommissioned under Type II or Type III,

depending on the total activity of 14C or 3

H possessed under the license, and the authorized use of the

radioactive material. LR/PMs should contact DWM/NMSS for guidance on which decommissioning Type is

appropriate for their particular situation 

2605 - 8 - Issue Date: 11/12/96

NRC staff should refer to Section 8 of the NMSS

Decommissioning Handbook for the procedures to be followed in

decommissioning nuclear facilities under Type I.

b. Type II Review

Facilities decommissioned under Type II would have used

licensed material in a manner that would not be expected to

result in its release into the environment, not activate

adjacent materials, or not be expected to result in

persistent contamination of work areas. However, these

licensees would not be able to demonstrate the radiological

status in accordance with the criteria discussed under the

Type I decommissioning above. Type II decommissioning would

include licensees that: 

1. Possess and use only sealed sources, but cannot

demonstrate that the sources did not leak while in

the licensee's possession (i.e., leak tests are

not available or indicate contamination >0.005

μCi); or 

2. Possess unsealed radioactive material with T1/2 < 60

days but the maximum activities authorized under

the license have not decayed to less than the

quantity specified in 10 CFR Part 20, Appendix C

at the time the licensee requests license

termination; or

3. Possess unsealed radioactive material with T1/2 > 60

days but < 120 days3.

Type II decommissioning would not require the submission of

a DP to NRC. However, these licensees would be required to

submit a completed NRC Form 314, or equivalent, determine the

radiological status of facilities, remove residual

radioactive material, if necessary, and demonstrate that the

facilities meet NRC's requirements. This demonstration could

be made by submitting the results of a FSS to NRC for review

and approval, or by other suitable means. 

Typically, NRC staff would perform a Closeout Inspection at

facilities decommissioned under Type II. Based on prior

management of licensed material at the facility, and the

results of the licensee's Final Status Survey, NRC may

perform a Confirmatory Survey at these facilities. NRC staff

should refer to Section 9 of the NMSS Decommissioning

Handbook for the procedures to be followed in decommissioning

facilities under Type II.

c. Type III Reviews
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All licensees that are required to submit a DP in accordance

with NRC regulations at 10 CFR 30.36(g)(1), 40.42(g)(1), or

70.38(g)(1), as well as all Part 72 licensees, would

decommission their facilities under Type III or Type IV. The

decommissioning will be categorized as a Type III or Type IV

decommissioning based on the complexity of the

decommissioning and the NRC staff actions required to comply

with NEPA.

Facilities decommissioned under Type III would have used

licensed material in a manner resulting in: releases into the

environment; activation of adjacent materials or persistent

contamination of work areas. Type III decommissioning would

include licensees that: 

1. Qualify for a categorical exclusion under 10 CFR

51.22 (c); and

2. Will decommission facilities in accordance with

NRC's criteria for unrestricted use.

Type III decommissioning would always involve the development

and submission of a DP by the licensee (including

characterization, financial assurance, health and safety,

survey plans, etc.). NRC staff would notice the receipt of

the DP in the Federal Register, and review and approve the DP

prior to commencement of decommissioning activities by the

licensee. NRC staff would also provide the public with the

opportunity to comment on the DP prior to approval. Review

of the DP would be documented using a checklist. Approval of

the DP would typically be done as a license amendment that

would incorporate the DP as part of the license. Upon NRC

approval of the DP, the licensee or responsible party would

perform the decommissioning, including a FSS. Based on the

licensee's prior performance, NRC may conduct a confirmatory

survey to ensure that the site meets NRC's criteria for

unrestricted use. NRC staff should refer to Section 10 of

the NMSS Decommissioning Handbook for the procedures to be

followed in decommissioning facilities under Type III.

d. Type IV Review

Facilities decommissioned under Type IV would have used

licensed material in a manner that has resulted in its

release into the environment, activated adjacent materials or

resulted in persistent contamination of work areas. Type IV

decommissioning would include licensees that: 

1. Would not qualify for a categorical exclusion

under 10 CFR 51.22 (c); or

2. Intend to decommission facilities such that

residual radioactive material may remain at the

site in excess of the levels specified in NRC's

criteria for unrestricted use.
2605 - 10 - Issue Date: 11/12/96

Type IV decommissioning would always involve the development

and submission of a DP by the licensee (including

characterization, financial assurance, health and safety,

survey plans, etc.). NRC staff would notice the receipt of

the DP in the Federal Register, and review and approve the DP

prior to commencement of decommissioning activities by the

licensee. NRC staff would also provide the public with the

opportunity to comment on the DP prior to approval. Review

of the DP would be documented using a SER. Approval of the

DP would be done as a license amendment which would

incorporate the DP as part of the license. In addition to

the review of the DP documented in the SER, approval of the

licensee's amendment request would be supported by an EA

and, if appropriate, a FONSI. If the EA results in a

determination that the environment would be impacted by the

decommissioning, NRC staff will document this impact in an

EIS.

Upon NRC approval of the DP, the licensee or responsible

party would perform the decommissioning, including a FSS.

NRC staff would generally conduct a confirmatory survey to

ensure that the site meets NRC's criteria for license

termination. NRC staff should refer to Section 11 of the

NMSS Decommissioning Handbook for the procedures to be

followed in decommissioning facilities under Type IV.

06.02 Decommissioning Plans. The objective of the DP is to

describe the activities and procedures that a licensee intends

to undertake to remove residual radioactive material

attributable to licensed activities at the facility to levels

that meet NRC criteria in sufficient detail to allow NRC staff

to determine whether decontamination of the facility can be

accomplished safely. To the extent that licensed material is

mingled with elevated (i.e., above background levels) naturally

occurring radioactive material (NORM) the elevated NORM is also

remediated in decommissioning. NRC regulations at 10 CFR Parts

30, 40, 70, and 72 require that certain information be provided

by licensees in the DP. The information that licensees are

required to include in the DP is summarized below. This

information is discussed in detail in the NMSS Decommissioning

Handbook.

a. Content of Decommissioning Plans 

NRC regulations at 10 CFR 30.36(f)(4)(ii) and (iii),

40.42(f)(4)(ii) and (iii), 70.38(f)(4)(ii) and (iii), require

that DPs contain "...a description of the planned

decommissioning activities" and "...a description of the

methods used to ensure protection of workers and the

environment against radiation hazards during

decommissioning." NRC regulations at 10 CFR 72.54(f)(2),(3)

and (6) require that DPs contain "...the choice of the

alternative for decommissioning with a description of the

activities involved", "...a description of the controls and

limits on procedures and equipment to protect occupational

and public health and safety" and "...a description of

technical specifications and quality assurance provisions in
Issue Date: 11/12/96 - 11 - 2605

place during decommissioning." Generally, this information

is developed by the licensee after determining the

radiological status of its facility. The DP is submitted to

NRC for review and approval as a license amendment request.

NRC staff should refer to Section 11 of the NMSS

Decommissioning Handbook to determine the information that

should be included in the decommissioning plans, as well as

the procedures for reviewing the plan. 

b. Site Characterization

NRC requirements for decommissioning under 10 CFR

30.36(f)(4)(i), 40.42(f)(4)(i), 70.38(f)(4)(i), and

72.54(f)(1), require that proposed DPs include "...a

description of the conditions of the site or separate

building or outdoor area sufficient to evaluate the

acceptability of the plan." Licensees can develop this

information using institutional knowledge about radioactive

material use at their facility, by performing a site

characterization survey, or by a combination of these

methods. Some licensees may require heightened attention by

NRC staff during characterization planning. For these

licensees it may be appropriate for NRC staff to request

submission of site characterization plans or reports or to

meet with the licensee prior to, or during, site

characterization. The NRC staff should refer to Section 12

of the Decommissioning Handbook for information on the

development of site characterization information, as well as

the criteria for requesting early submission of site

characterization information by licensees. 

c. Financial Assurance for Decommissioning

NRC regulations at 10 CFR 30.36(f)(4)(iv), 40.42(f)(4)(iv),

and 70.38(f)(4)(iv) require that DPs contain "...an updated

detailed cost estimate for decommissioning, comparison of

that estimate with present funds set aside for

decommissioning and a plan for assuring the availability of

adequate funds for completion of decommissioning." NRC

regulations at 10 CFR 72.54(f)(5) also require Independent

Spent Fuel Storage Installations to provide this information,

along with information on a means to adjust cost estimates

and funding levels over any storage or surveillance period.

This information is typically presented to NRC for review and

approval in an individual license application as the

Decommissioning Funding Plan or Certificate of Financial

Assurance. This information is updated in the DP. NRC staff

should refer to Section 14 of the NMSS Decommissioning

Handbook for information on financial assurance for

decommissioning and the procedures to be followed to review

the licensee's financial assurance mechanism.

d. Final Status Survey Plans
2605 - 12 - Issue Date: 11/12/96

Licensees wishing to terminate their licenses must

demonstrate to NRC that residual radioactive material at

their facility attributable to past licensed operations does

not exceed NRC criteria for release of the facility. NRC

regulations at 10 CFR 30.36(f)(4)(iv), 40.42(f)(4)(iv),

70.38(f)(4)(iv) and 72.54(f)(4) require that all DPs contain

a description of the planned final radiation survey to

demonstrate that the facility meets NRC's criteria for

release and termination of the license. In addition, NRC

regulations at 10 CFR 30.36(i)(2), 40.42(i)(2), 70.38(i)(2)

and 72.54(k)(2) describe the information that must be

submitted to NRC to support a demonstration that a licensed

facility is suitable for release from regulatory control.

NRC staff should refer to Section 16 of the NMSS

Decommissioning 

Handbook to determine what information should be presented in

Final Status Survey Plans and Reports. 

06.03 Inspections During Decommissioning

Manual Chapter 2602, "Decommissioning Inspection Program for

Fuel Cycle Facilities and Materials Licensees" establishes the

inspection program for fuel cycle and materials licensees

undergoing decommissioning. NRC has developed Inspection

Procedure 87104 "Decommissioning Inspection Procedure for

Materials Licensees" and Inspection Procedure 88104

"Decommissioning Inspection Procedure for Fuel Cycle

Facilities." These inspections should confirm safe performance

of decommissioning, including checks of the quality of the

licensee's final survey. All NRC personnel implementing the

decommissioning inspection program shall use the guidance

identified in MC-2602 and the Decommissioning Inspection

Procedures. 

06.04 Confirmatory Surveys

After acceptance of the licensee's final survey report, NRC may

conduct a confirmatory survey. Inspection Procedure 83890

discusses the procedures to be followed to determine whether a

confirmatory survey is required at a licensed facility.

Inspection Procedure 83890 also summarizes the procedures to be

followed to perform closeout inspections and confirmatory

surveys. The confirmatory survey develops radiological data of

the same type as that presented by the licensee, but is usually

limited in scope to spot-checking conditions at selected site

locations, comparing findings with those of the licensee, and

performing independent evaluations of the data developed by the

two surveys. NRC uses the report of this survey in supporting

a decision on the licensee's application to terminate a license

and release the site. The confirmatory survey is not intended

nor designed to duplicate or augment the licensee's FSS. NRC's

regulations do not include specific requirements for the

confirmatory survey. 

Facilities decommissioned under Type III will require a

confirmatory survey and a closeout inspection, unless
Issue Date: 11/12/96 - 13 - 2605

inspections by NRC during the licensee's FSS confirm that the

licensee's survey will be of sufficient quality to demonstrate

that the facility meets NRC criteria for termination of the

license. NRC staff shall assign higher priority for conducting

confirmatory surveys at sites that may pose a greater potential

threat to the public health and safety if not remediated in

accordance with NRC criteria. This approach would allow the

release of some facilities from regulatory control based solely

on past operations and performance, the staff's confidence that

the facility was adequately remediated by the licensee, and a

closeout inspection that does not indicate that additional

issues remain unresolved at the facility. Facilities

decommissioned under Type IV generally will require a

confirmatory survey and closeout inspection by NRC staff.

NRC staff should refer to Section 17 of the NMSS

Decommissioning Handbook for information and procedures to be

followed in developing Confirmatory Surveys.

06.05 Partial Facility Decommissioning

In most instances a licensee will request termination of its

license with the intent of releasing the entire site from

regulatory control. However, in some instances a licensee may

request that only a portion of its facility be removed from the

license. NRC requirements at 10 CFR 30.36(d)(1-4), 

40.42(d)(1-4), 70.38(d)(1-4), and 72.54(d)(1-3) describe the

conditions under which a licensed facility would be required to

commence decommissioning operations, which would also be

applicable to those instances where a licensee ceases

operations at a portion of its facility. 10 CFR 30.35(g),

40.36(f), 70.25(g) and 72.30(d) describe the requirements for

the maintenance of records pertaining to decommissioning

licensed facilities which would also apply to the

decommissioning of a portion of a licensed facility.

Generally, release of a portion of the licensed facility for

unrestricted use is accomplished in the same manner as the

release of the entire site or facility (i.e. by the licensee

developing a DP, as required, that includes site

characterization information and descriptions of remedial

activities; performing the remedial activities; and

demonstrating that the site meets NRC's current criteria for

release). However, when completed the decommissioned portion

of the facility will be released via amendment to the license,

rather than termination of the license. 

At facilities possessing broad scope licenses, radioactive

material usage may be terminated and resumed at separate

locations (e.g., individual laboratories within a building) at

the facility numerous times during the active phase of the

license. For this type of decommissioning, the licensee is not

required to notify NRC as described in 10 CFR 30.36(d), as long

as the licensee has not decided to permanently cease principal

activities at the entire site or in any separate building.

Also, because of the broad-scope nature of the license and the

limited scope of the decommissioning, the licensee would not be

required to submit a DP as described in 10 CFR 30.36(f)(1) and
2605 - 14 - Issue Date: 11/12/96

would not request an amendment to its license to describe this

change in areas of use. As such, the licensee would only be

required to maintain records of the decommissioning for review

by NRC per 

10 CFR 30.35(g).

The licensee's decommissioning and release of these separate

locations for unrestricted use must be accomplished and

documented in a manner similar to that described in this manual

chapter for licensee's facilities which are subject to NRC

review and approval prior to release for unrestricted use. To

ensure that broad scope licensees have adequately

decommissioned these separate locations, inspectors must

perform a detailed review of the licensee's decommissioning

records during each inspection and should consider performing

confirmatory measurements in those separate facilities the

licensee has released for unrestricted use.

NRC staff should refer to Section 18 of the NMSS

Decommissioning Handbook for the procedures to be followed to

release a portion of a licensed facility for unrestricted use.

06.06 License Termination

The final action required by the licensee after it has

completed remediation and adequately demonstrated that the

facility is suitable for release in accordance with NRC's

requirements is the submission of NRC Form 314. If the

licensee has satisfied all of the conditions for remediating

its site, NRC staff terminates the license for the site. For

sites listed on the SDMP and other non-routine sites, NRC

should inform the State agency that may have jurisdiction over

any hazardous chemical contamination and the U.S. Environmental

Protection Agency about the intent to terminate the license.

In addition, the termination is intended as final agency action

and should include appropriate language in the termination

letter to reflect this intent. NRC staff should refer to

Section 20 of the NMSS Decommissioning Handbook for the

procedures to be followed to terminate the license.

06.07 Formerly Licensed sites

In February 1995 NRC issued Temporary Instruction (TI)

2800/026, which outlines the procedures staff shall follow to

verify the status of formerly licensed sites for which there is

inadequate documentation in the docket file to demonstrate that

they were properly decommissioned. Staff should refer to TI

2800/026 and Section 21 of the NMSS Decommissioning Handbook

for guidance on the appropriate procedures to be followed to

assess the status of formerly licensed sites.

END