ML20045A495

Forwards ANS Draft Std ANS-15.10, Decommissioning of Research Reactors, for Review & Comments

ML20045A495
Person / Time
Issue date:	04/08/1993
From:	Weiss S Office of Nuclear Reactor Regulation
To:	Joseph Austin, Cool D, Liza Cunningham NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS), Office of Nuclear Reactor Regulation, NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
References
NUDOCS 9306100388
Download: ML20045A495 (29)

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MEMORANDUM FOR

Lemoine'Cunningham, Chief.

l Radiation Protection Branch i

n Division of.. Radiation ~ Safety and Safeguards l

N Office of Nuclear. Reactor Regulation W

P John-H.LAustin,' Chief.

3 Decommissioning and Regulatory Issues Branch i

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s Division' of Low-Level Waste Management.

K and~ Decommissioning Office of Nuclear Materials Safety' and Safeguards 1

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Donald A. Cool, Chief Radiation Protection and Health Effects Branch

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Division of Regulatory Applications 1

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- Office of Nuclear. Regulatory Research FROM:

Seymour H. Weiss,' Director Non-Power Reactors and Decommissioning Project Directorate-Division of Operating Reactor Support j

Office of Nuclear Reactor Regulation p

SUBJECT:

REVIEW 0F AMERICAN NUCLEAR SOCIETY STANDARD Enclosed is'a copy of ths American Nuclear; Society draft standard ANS-15.10,

~" Decommissioning of Research Reactors" (Revision).: Please review this draft and-)rovide us any comnents you may have.. To meet the ANS voting deadline,

. hic 1 cannot'be extended, your comments should be returned to us by May 28, w

1993.

If you have any~ questions, contact Al Adams at 504-1127.

Original signed by:

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.Seymour H. Weiss, Director Non-Pouer ReactorsLand Decommissioning

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Project' Directorate Division'of Operating Reactor Support Office of Nuclear Reactor Regulation

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ANS 15.10 I

LForeword (This forward was prepared to provide a background and' explain the need' for non-power reactor standards and criteria concerning the use of those standards.)

The American Nuclear Society Standards Secretariat established Subcommittee ANS-15 in the fall of 1970 with the task of preparing a i

standard for the operation of research reactors. In January 1972, this

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charter was expanded to the multiple tasks of preparing all standards i

for research reactors. To implement this enlarged responsibility, a number of subcommittee working groups were established to develop.

standards for consideration, and complementary action by i

Subcommittee ANS-15. ANS-15.10 is one of these groups.

In March 1979, Working Group ANS-15.10 was assigned the task of

.i developing a draft standard for decommissioning of research reactors.

Since that time changes in regulatory policy.were incorporated into this current revision. The ANS-15.10 Working Group membership at the time of completion of the standard was:

M.H. Voth, Chairman, Pennsylvania State University.

J.J. Adler, TLG Engineering, Inc.

.i W.E. Austin, Westinghouse Electric Corporation J.A. Christian, Chem-Nuclear Environmental Services, Inc.

1 T.S. LaGuardia, TLO Engineering, Inc.

M. Mendonca, U.S. Nuclear Regulatory Commission T.R. Schmidt, Sandia National Laboratory Present decommissioning regulations for reactors are contained in the Code of Federal Regulations, Title 10, " Energy," Part 50, " Licensing of L

Production and Utilization Facilities," which addresses'primarily the financial qualifications of the applicants. The' policy for licensed power reactors is contained in U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide 1.86, " Termination of Operating Licenses for Nuclear Reactors," which was issued in June 1974 and is generally used as a basis for decommissioning activity. Currently, the NRC is in the process of developing more specific criteria on decommissioning in g

an effort to generate a more explicit overall policy. This standard provides needed procedures, criteria, and standardization for the decommissioning of research reactors which is also' appropriate for test reactors.

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ANS 15.10 As a caution, because of the current developmental activity by the -

_ NRC in'this area, it should be recognized that some of the procedures L-and criteria stated in this standard are not based on existing regulations, and that as regulations are developed and approved, such -

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procedures and criteria may be subject to change.

In preparing this standard, the intent has been to specify objectives-E that will:

(a)

Assist in implementing regulatory requirements.

(b)

Be a significant aid in planning and executing decommissioning activities.-

The family of American National Standards developed by ANS-15 for research reactors are:

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(List of Standards) f 1

The membership of Subcommittee ANS-15 at the time of its approval of this standard was:

(List of Members) i Consensus Committee N17 Research Reactors, Reactor Physics, Radiation Shielding, and Computational Methods, had the following membership at the time it reviewed and approved this standard:

T.M. Raby, Chairman A. -Weitzberg. Vice-Chairman (List of Members) 1

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ANS 15.10

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TABLE OF CONTENTS Section Page 1.

I NTR O D U CTI O N.............................................

I 1.1 Scope.................................................

I a

2.

D E FI N ITI O N S...............................................

1 3.

DECOMMISSIONING ALTERNATIVES...........................

3.

3.1 S AFSTO R.............................................. 4 3.2 E N TO M B..............................................

5-33 D E CO N...............................................

6 4.

P LAN N I N G................................................. 7 4.1 Design Period Planning.................................... 7 3

4.1.1 Occupational Exposure................................

8 4.1.2 Accessibility.. '.......................................

8 4.13 Decontamination................................... 8 4.1.4 Removal Feasibility Verification.........................

9-4.1.5 Materials of Construction.............................. 9 i

4.1.6 Administrative Planning............................... 9 4.1.7 Financial Planning..................................

10 -

4.2 Operation Period Planning................................

11 4.2.1 Preparatory Work.................................. - 11 4.2.2 Financial Planning..................................

11 43 Decommissioning Planning................................

12 43.1 Scope of D_ecommissioning ' Activities....................

13 43.2 Radiological Characterization..........................

14 433 Radioactivity Material Inventory........................

15 1

43.4 Decommissioning Plan....... '........................

16

~ 43.5 Activity Specifications...............................

17 43.6 Detailed Work Procedures............................

18 43.7 Maintenance and Surveillance.........................

18 43.8 Quality Assurance.................................

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5.

UNRESTRICTED USE CRITERIA..............................

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5.1 Surface Radioactive Contamination Criteria.................... - 19 '.

5.2 Neutron-activated Radioactivity Criteria.......................

19 5.3 Soil and Groundwater Contamination or Activation Criteria........

20 5.4 Ex ce p t i o ns............................................

24

'i 6.

S U R V EI LLAN C E............................................

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l 6.1 Radiation Safety...................................

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6.2 Fire Protection.................................... ~ 26 '

6.3 Physical Se cu rity...................................

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6.4 Structu ral Integrity.................................

27-6.5 Environmental Monitoring...........................

28 7.

ENVIRONMENTAL ASSESSMENT.............................

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7.1 Regulatory Requirements............................

28 7.2 Environmental Impact Information....................

29 8.

Q UALITY ASS URAN CE......................................

30 8.1 S A F STO R.............................................

31 8.2 ENTOMB.....

......................................31 8.3 DECON............................................

32 9.

REPORTS / DOCUMENTATION................................

32 9.1-Design /Constru ction.....................................

33 9.2 Op e ratio ns............................................

33 9.3 D e commissio ning.......................................

34 10.

R E FE R E N CES...............................................

35 Appendix A ' Terminology for Decommissioning Alternatives............. -...

38 Appendix B Activity Specification Format..............................

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Appendix C - Discussion of Environmental Impact Factors..................

41.

Appendix D List. of Decommissioned Reactors............................. 45 References for Appendices '................................

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ANS 15.10 TABLES Table 5-1

. Acceptable Surface Contamination Levels...................

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' Table 5-2 Maximum Soil and Groundwater Contamination Levels '..........

23 Table C-1 List of Environmental Factors.............................

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ANS 15.10

'l Decommissioning of Research Reactors 2

3 1.

INTRODUCTION 4

1.1 Scope 5

This standard provides requirements and criteria for the decommissioning 6

of research reactors and includes decommissioning alternatives, planning, radiation 7

criteria, surveillance and maintenance, environmental impacts, quality assurance, and 8

reports and documentation.

9 10 2.

DEFINITIONS 11 As Low As is Reasonably Achievable (ALARA). To make every reasonable 12 effort to maintain exposures to radiation as far below the dose limits as is practical, 13 consistent with the purpose for which the permitted or licensed activity is undertaken, 14 taking into account the state of technology, the economics of improvements in relation to 15 the state of technology, the economics of improvements in relation to benefits to the 16 public health and safety, and other societal and socioeconomic considerations, and in 17 relation to utilization of nuclear energy and permitted or licensed materials in the public 18 interest.

19 20 Decommissioning. Decommissioning is defined, for a reactor facility, as 21 the measures taken at the end of the facility's life to remove all radioactivity to

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acceptable levels so as to terminate the. license or operating authorization. For the 2

scope of this standard, only the special nuclear, source, and byproduct materials are

'3 covered. All other hazardous substances should be handled in accordance with standard r

4 industry procedures or guidelines.

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Non-Power Reactor (NPR). See research reactor 7

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Research Reactor. A research reactor is defined as a device designed to -

9 support a self-sustaining neutron chain reaction for research, developmental, educational, 110 training, or experimental purposes, and which may have provisions for production of 11 radioisotopes. [ Note: For the purposes of this standard, test and non-power reactors fall 12 within this definition.]

13 14 Research Reactor Facility. Research reactor facility includes all areas 15 within which the owner or operator directs authorized activities associated with the 16 reactor.

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18 Shall, Should, and May. The word "shall"is used to denote a requirement; 19 the word "should" to denote a recommendation; and the word "may" to denote 20 permission, neither a requirement nor a recommendation.

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Test Reactor. See research reactor 2

4 l3 Unrestricted Use. The use of a facility, material, equipment or waste when

'4 the radioactive content on surfaces of or inherent within any portion of it is sufficiently 5

low to pose no unacceptable health hazard to any indisidual or group of individuals -

6-regardless of any future use or location of the facility, material, equipment, or waste.3 7-l 8

3.

DECOMMISSIONING ALTERNATIVES 9

The ultimate disposition of a reactor facility upon completion of operations will-l s

10 result in either (1) the retention of certain radioactive materials in-situ or (2), the 11 complete removal of required radioactive materials from the facility to an approved 12.

disposal site. Retention of materials.in situ will require continuation of a license or-13 charter and is not a decommissioning alternative. Three major recognized--

14 decommissioning alternatives leading to the ultimate disposition are mothballing, in; place

. 15 entombment, and removal of radioactive components and dismantling.[1,9]2 A

-16 decommissioning plan shall be prepared and approved by the licensing or chartering 17 agency. Decommissioning should be accomplished without significant' delay unless such 18 delay is necessary to protect public health and safety. The pseudo acronyms SAFSTOR, 19 2

Unrestricted use addresses only health hazards and not potential industrial uses 20 where

~ materials with low radioactivity might impact, i.e. sensitive radiation 21 detectors.

22, 2

Numbers in brackets refer to corresponding numbers in Section 10, References.

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~ ~ANS l'5.10 1-ENTOMB, and DECON are used herein to identify the three' recognized alternatives 1

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4 3.1 SAFSTOR 5~

SAFSTOR means to fix and maintain the facility so that the risk to publicL 6

health and safety is acceptable for the period of storage. The duration of the SAFSTOR' 7

alternative depends on several factors, including the structural condition of the facility,

'8 the lifetime of the residual radioactivity, the future use of the facility or site, or both, and 9'

the cost of the security / maintenance smveillance program. During this protective..

.10 storage period, decay of the shorter life isotopes occurs which assists in reducing the-

-11 dose to future decommissioning personnel. This approach is consistent.with ALARA 12 principles. Following the period of SAFSTOR, the facility ultimately'must be -

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'13 decommissioned using the ENTOMB or DECON alternative. SAFSTOR shall' include 14 the following actions:

15 (1)

Performance of a comprehensive characterization survey for radioactive, 16-materials.

17 (2)

Removal of all fuel assemblies from the facility.

L18 (3)

Removal of radioactive fluids and wastes from the facility.

19-(4)

Removal or stabilization of contamination in all accessible areas. Included 20.-

JAppendix A present a summary of terminologies used in various places to define :

3 21 decommissioning alternatives. '

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1-in this are measures to prevent the spread of contamination during the

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protective storage period.

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(5)

Operation of all required life support and protection systems, such as.

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heating, ventilation, air conditioning, radiation monitoring, fire protection,.

5-and environmental monitoring systems, as appropriate.

6 (6)

De-energizing non required systems.

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7 (7)

Isolation and sealing of remaining radioactive areas.

8' (8)

Performing routine security. maintenance, and surveillance activities.

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1 10 3.2 ENTOMB

.11 In-place entombment (ENTOMB) consists of sealing of all the rema~ining-j 12 highly radioactive or contaminated components (e.g., reactor structural components) i 13 within a structure integral with the biological shield, after having all fuel assemblies,.

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14 radioactive fluids, and wastes, and certain selected components shipped off site. The 1

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. structure should provide integrity over the period of time in'which significant ' quantities.

16 (greater than Table 5-1 levels) of radioactivity remain with the ' material in the j

.17 entombment. This decommissioning alternative may be precluded for a reactor facility 18 that has had a significant operating history, due to the presence of long-lived activation 19:

products in the reactor. The time to achieve unrestricted release would be inordinatelyL 20 long and structuralintegrity of the entombment could not be assured over the period, l

21-ENTOMB shall include the following actions:

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1; (1)

Performance of a_ comprehensive characterization survey for radioactive a

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3 (2)

Removal of all fuel assemblies from the facility.

4:

(3)

Removal of radioactive fluids and wastes from the facility, j

5 (4)

Removal or stabilization of contamination in all areas. Included in this are_

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measures to prevent the spread of contamination during the protective 7

storage period.

84 (5)

Sealing of the remaining reactor components that may include use of the_

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existing structure.

10 (6)

Performing routine security, maintenance, and surveillance activities.

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'12 3.3 DECON F

.131 The removal of radioactive components'and' dismantling (DECON) l 14-

- alternative consists of removal of fuel assemblies, radioactive fluids and waste, and other '

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l15 materials having activities above accepted unrestricted activity levels (Table 5-1). The -

-16 facility owner may then have unrestricted use of the site. _If the facility owner so desires -

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the remainder of the reactor facility may then be dismantled and all vestiges removed for-IST

. disposal. This alternative shallinclude the following actions:

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(1)

Performance of a comprehensive characterization survev for radioactive:

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materials.

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21 (2)

Removal of all fuel assemblies from the facility.

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1-(3)

Decontamination of structural surfaces to allow unrestricted access to th'e '

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facility.

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(4)

Removal from the facility of radioactive material which would prevent.

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. unrestricted use of the facility.

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5 (5)

Obtain authorization for unrestricted use from the cognizant licensing or q

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chartering agency (ies).

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'8 4.

PLANNING j

-i 9-Planning for decommissioning of research reactors should begin during the facility q

I 10 design period. This planning should be implemented during construction and operation 11-to facilitate decommissioning feasibility, and minimize occupational dose and overall 12' cost. Such planning should anticipate the need for additional data, shielding, 13 decontamination, waste handling and disposal, and_ site and facility access.

1 14-15 For existing operating reactors, decommissioning planning should be included in' d

-16 the design of major facility modifications.. For these reactors, preparatory 17

. decommissioning work, including ordering special tools or equipment and collecting 18 reliable facility and site data, should be planned and implemented during the operating j

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Whether a research reactor is being designed or is operating, financial planning i

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11 for ultimate decommissioning is necessary.to ensure adequate funds when they are 2

- needed.

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3 4-4.1 Design Period Planning 5

In designing a research reactor, the architect-engineer should consider the i

6 requirements for facility decommissioning. The following discussion identifies certain 7

areas where designers can simplify dismantling activities.

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-10 4.1.1 Occupational Exposure f

11 The design of the systems and structure should protect decommissioning 12 personnel from excessive radiation exposure. For highly radioactive components, 13 techniques such as radiation shields, rapid disassembly design, remote chemical 14 decontamination connecticos, and adequate cutting and removal' space should be -

15' included.'

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16 17 4.1.2 Accessibility

'18 The facility design should include sufficient platforms, doors,

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l passageways, cranes, portable hoist supports or rails, lighting, and power ' supplies

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- (pneumatic and electrical) in potentially high dose rate areas.

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1.

To facilitate the removal of radioactive material from the facility,

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2; adequate equipment hatches should be provided and floor loading capacities should l

-3 support heavy packages and casks. Roads to the facility should have sufficient load j

4 carrying capacity to support the heaviest anticipated shipments (component, container.

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5 shielding, and vehicle).

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'-7 4.1.3 Decontamination 8

Piping, component, and structure designs should allow for internal and 9

external surface contamination by providing for decontamination. Nondrainable cavities 10 in piping and components, as well as inaccessible interstices on welded structures should 11 be minimized. Exposed concrete surfaces should have smooth finish coats and 12 waterproof coatings to prevent penetration of contamination.

13 14 4.1.4 Removal Feasibility Verification 15 Design-phase engineering studies should verify the feasibility.of 16 dismantling and removing contaminated or activated components, systems, and 17 structures.

18 19 4.1.5 Materials of Construction 20 The design of the components that will be exposed to neutrons should 21 include materials that minimize the activation of long-lived isotopes, to reduce 9

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'l radionuclide inventory and potential occupational dose. Where material elemental

2 compositions in these components cannot be reduced for reasons of strength, corrosion.

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3i resistance, or availability, alternative designs should explore minimizing the_ incident'

~4 neutron flux.

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'6' Typical radionuclides of concern and their characteristic decay data are -

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given in Reference [1].

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4.1.6 Administrative Planning

-i 10 To ensure that future decommissioning planning may be efficient and "j

11 complete, a formalized administrative program should be implemented during the Design

.i L12 and Construction period to collect and archive applicable data during all phases of...

'13 facility life. Section 9 of this document provides criteria for types of reports and -

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documentation to be' retained to facilitate decommissioning planning.

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16-4.1.7 Financial Planning i

i 17 Planning prior to facility construction should include a preliminary _

18 estimate of the facility decommissioning costs.d The funding amount for research i

I 19 reactors shall be based on a facility-specific cost estimate, or on generic cost studies such

!a 4 ' NRC licensees are required to submit a decommissioning report and funding plan

-l 20 21 pursuant to References [10) and [11).

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'I as in Reference [7] with suitable adjustments to account for facility-specific differences.

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'3 Decommissioning funding methods include:

4 Prepayment - trust, escrow accounts, certificates of deposit or 5

other investments; i

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. Guarantees - surety bonds, letters of credit, insurance or parent

_7 company guarantees; 8

. External Sinking Fund - trusts, escrow accounts or certificates j

9-of deposit coupled with a guarantee method. An external sinking 10' fund shall be segregated from owners assets and outside the 11 owner's administrative control; 12

. Statement of Intent [ Government Agency] - funds for 13 decommissioning will be obtained when necessary.

14 15 The facility owner should consult the cognizant licensing or 16 chartering agency (ies) for specific requirements. Additional criteria can be found in-

.17 Reference {8].

18 19 4.2 -

Operation Period Planning 20 Decommissioning planning during operation of the research reactor can

~21 simplify the decommissioning program and achieve significant reductions in cost, 11 P

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occupational radiation exposure, and program duration. The following discussion 2

identifies certain operational activities to simplify decommissioning.

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4 4.2.1 Preparatory Work i

5 Prior to final shutdown, the facility operator should initiate 6

preparatory activities for decommissioning, including preparing preliminary estimates of.

7 the amount and composition of radioactivity in contaminated and activated components.

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If immediate removal is chosen, special tools and equipment should be designed, 9

procured, and tested during facility operation, to prevent unnecessary delays. The

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10 revised technical specifications and the decommissioning plan (see Section 4.3) should 11 also be prepared prior to final shutdown.

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13 4.2.2 Financial Planning 14' The need for reassessment of the financial plan should be reviewed

.~15 at least annually for inflation, and at least once every five years for other matters.'. The 16 five year reassessments should consider the effects of facility modifications, regulatory 17 changes, decommissioning technology improvements, and decommissioning services 18 (decontamination, removal, shipping, disposal). The financial plan should be adjusted as 19 necessary. Specific regulatory agencies may require more frequent reassessments and 1

20 adjustments.-

21 12

~ ANS 15.10

'1 Approximately five years prior to the projected end of operation of 2'

the reactor, the owner should submit a preliminary decommissioning plan with a revised L3 cost estimate. The revised estimate should assess factors that could affect planning for

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decommissioning. Adjustments to the level of funding shall be made at that time. No 5

credit shall be taken for fund growth from interest earned on the fund balance beyond a

6' the shutdown date.

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8 Withiri two years prior to final facility shutdown, the owner shall 9:

prepare a revised cost estimate and adjust the funding amount to assure all funds 10 necessary to complete decommissioning will be available at shutdown.

11 12 The facility owner should consult the cognizant licensing o'r

13 chartering agency (ies) for. specific requirements.

14

15 4.3 Decommissioning Planning 16-Planning the actual decommissioning of a research reactor shall include the f

17 -

major elements identified in the following subsections. One year prior to final shutdown,.

'18.

. the owner should prepare a final decommissioning plan for submittal to the cognizant 19 licensing or chartering agency (ies).

20 21 4.3.1 Scope of Decommissioning Activities 22 The facility's systems, components, structures and operating history 13

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required for decommissioning. This should include an evaluation of the equipment, 2-systems, or structures that may be contaminated or activate', and determination of the.

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-_3 technical specifications and quality assurance requirements for decommissioning. Unique-4 factors specific to the facility should be reviewed to determine potentialimpacts on j

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' decommissioning, such as: Reactor utilization / operating history; leaks or spills that may-6 have contaminated subsurface structures or soil; unusual radionuclides from activation of.

7-materials, construction of experiments, or production activities; presence of hazardous 8-materials or mixed wastes; facility construction layout or materials that facilitated 9-distribution of radioactivity; or presence of other nuclear facilities at the site. Proper i

10 preparation, administration and oversight are integral to decommissioning activities. A i

11 safety assessment of proposed decommissioning tasks on occupational and public health 12 and safety is often required by the cognizant licensing or chartering agency (ies) to.-

.13-demonstrate protection of the public and that occupational radiation exposure is-14 maintained as low as reasonably achievable. A description of the project management -

15 plan for decommissioning, including organizations, responsibilities, training,, and 16 contractor assistance is essential in defining the scope of decommissioning activities.

17 18 19 4.3.2 Radiological Characterization 20 A thorough radiological characterization program should be j

~21 performed for the structures involved and the environs surrounding the affected 22 structures. The purpose of the characterization program centers on the need to obtain j

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. specific radiological data concerning areas of the facility that may h' ave become internally' 2-or externally contaminated or activated during the facility's operation. This data will be-3 needed for the following:

Detailed decommissioning planning purposes and determination of.

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effective and appropriate decontamination and dismantling 6

technologies.

Planning radioactive material disposal, assessing potential hazards 7

8 during decommissioning and determining ALARA controls.

Predicting personnel exposure through calculations and dry runs of l

9 10 decommissioning activities.

11 The scope of the radiological characterization program should 12 address the following:

Structural fixed and removable surface' contamination and area dose 13

.14 rates;

. 15 System and component internal contamination and contact dose

-16 rates; Reactor bioshield structure and component activation; 17' Subsurface contamination (soil under structures);

.18 19 Environmental contamination (soil outside of building).

20 21 The characterization program should, as a minimum, obtain the 122 following information based on measurements, calculations, and samples:

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- Location. surface area, contamination levels, and radionuclides 2

identified on structural surfaces:

Depth of contamination penetration into surfaces; 3

Location, volume, and radionuclide activity levels of contaminated j

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soils; i

Location, dimensions, volume and neutron activated radioactivity

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-7 levels of contaminated equipment, ducts, fixtures, etc.;

Area and component radiation dose rates; 8

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- Calculation of radioactivity levels caused by activation of the 10 bioshield and associated reactor components, with verification by q

11 comparison'of calculated and measured gamma dose rates.

12 13 4.3.3 Radioactivity Material Inventory 14 The inventory of radioactive materials shall be estimated using data -

'15.

obtained from the radiological characterization and based upon assumptions from the 16 review conducted per Section 4.3.1. The estimated inventory should include radioactive 17 material volume, and radioactivity by radionuclide for each individual waste stream to be 18

- generated. Waste streams may generally include:

19-

- Contaminated concrete' debris; 20

- Contaminated soil; 21

- Dry active waste; 22

- Activated components;

' 23 Contaminated piping and equipment; 16

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- Activated concrete; -

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- Activated lead (mixed waste);

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- Contaminated lead (mixed waste);

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- Contaminated asbestos (mixed waste);

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- Contaminated liquid; 6'

- Evaporator concentrates and filters; e

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- Deionizing resins.

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The inventory will be used to estimate waste disposal volume and.

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_ planning dismantling, decontamination and waste treatment, packaging, transport,'and -

11-disposal activities.

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13 4.3.4 Decommissioning Plan l

14 The decommissioning program shall be described in a-

-15 Decommissioning Plan. The plan shall contain the following:

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- Facility description; 17-

- Facility operating history; i

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- Radiological status of the facility; 191

- Selection and justification of decommissioning alternative;--

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- Decommissioning organization and responsibilities; 21

- Applicable regulations and standards; 22

- Personnel training and qualification requirements; i

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'ANS 15.10 1

1

'1

- Occupational, environmental and radiation protection:

.2'

- Cost estimate and funding plan;

.3

- Description of dismantling and decontamination tasks and

-l 4

activities and associated radiation exposure';

l 5

- Schedule of activities; 6

- Security plan;

'7

- Summary of emironmental assessment; Decommissioning safety assessment; 8-Emergency plan;.

9 Waste management plan; 10

~11

- Waste disposal plan; Final radiological survey plan and release criteria; 12 Quality assurance plan; 13 l

Decommissioning technical specifications, if applicable.

14 15' 16 The plan shall be approved by the cognizant licensing or chartering 17 agency (ies).

r

.18 -

'.19 4.3.5 Activity Specifications f

20 The major activities of the program shall be defined by written 21.

Activity Specifications that include the purpose, the description of the task _, the 22 applicable criteria, and the sequence of events. The criteria may include engineering _

i 18 t

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ANS 15.10 1

and technical requirements; health, safety, and environmental protection; waste 2

management requirements; quality control requirements; and reference to applicable 3

standards. Activity Specifications are used as the basic planning tool for the program.5 4

5 4.3.6 Detailed Work Procedures

.6-The work identified in the Activity Specifications shall be further 7

defined by detailed procedures. - These procedures shall provide the prerequisite 8

activities, the step-by-step instructions, the required equipment and associated equipment

[

9 operating parameters, the safety precautions, and the disposal methods (as applicable).

10-l 11 4.3.7 Maintenance and Surveillance 12 Plans shall be made for maintenance and surveillance _ (security and 13 radiological) during decommissioning activities and during the subsequent surveillance-14 period for the SAFSTOR or ENTOMB alternatives. These maintenance and 15-surveillance requirements shall be identified in the revised facility Technical

~

1 16 Specifications. Section 6, Surveillance, contains a detailed discussion of the maintenance 17-and surveillance requirements for the SAFSTOR and ENTOMB alternatives.

18 19:

4.3.8 Quality Assurance 20 The quality assurance program shall be prepared in accordance 21-with the requirements in Section 8, Quality Assurance.

-22 5Appendix B contains a suggested format for Activity Specifications.

19 i

M' g

L/

W ANS 15.10 1

5.

UNRESTRICTED USE CRITERIA 2

At the end of a research reactor's operating life, equipment, structures, and other 3

materials may be neutron activated, or radioactively contaminated, or both, on interior 4

or exterior surfaces. If an item's radioactivity is above unrestricted use limits, then the 5

item must be handled and dimosed of in accordance with applicable requirements. It 6

follows that materials containing radioactivity below these limits may be handled and 7

disposed of without consideration of radiation-related regulations. It should be noted 8

that in some locations State or local regulations exist where disposal or release of 9

materials containing radioactivity below licensing or chartering agency (ies). limits to 10 municipal landfills or sanitary sewers require permitting or special handling.

11 12 5.1 Surface Radioactive Contamination Criteria 13 Surface radioactive contamination may remain in situ if the levels do not 14 exceed the levels given in Table 5-1 [9,14].

15 16 5.2 Neutron activated Radioactivity Criteria 17 A general unrestricted use regulatory limit for application in 18 decommissioning actions has not been established for neutron-activated materials. For 19 activated materials to be released for unrestricted use, the radiation dose rate at one 20 meter from the surface of material should not exceed 5 microrem/ hour above 21 background or 10 millirem / year above background considering reasonable proximity and 22 occupancy.[12] To exceed these dose rates, the limit shall be determined on a case-by-20

()

.Q:

' ANS 15.10 I

case basis by the cognizant licensing or chartering agency (ies).

~

2-

'3-5.3 Soil and Groundwater Contarnination Criteria 4-Soil and groundwater contamination may remain in situ if the levels do not V

.5 exceed the levels given in Table 5-2.[14]

6 7-

.g-i i

.]

i 21

.t

^

ANS 15.10.

Table S-1 Acceptable Surface Contamination Levels [9,14]

- Nuclide*

Average

Maximm Removable

b bdt b

2 2

2 U nat U-235, 5,000 dpm a/100 cm 15,000 dpm a/100 cm 1,000 dpm a/100 cm -

U238, and associated decay products 2

2 2

Transuranics, 100 dpm/100 cm 300 dpm/100 cm 20 dpm/100 cm Ra-226, Ra 228 Th-230, Th-228 Pa-231, Ac-227, l-125,1-129 2

2 2

~

Th-nat, Th-232, 1,000 dpm/100 cm 3,000 dpm/100 cm 200 dpm/100 cm Sr-90, Ra-223, Ra-224, U-232, 1

1-126,1-131,I-133 2

2 Beta-gamma 5,000 dpm s-y/100 cm 15,000 dpm # y/100 cm 1,000 dpm 2

emitters (nuclides

1. -y/100 cm with decay modes t

other than alpha emission or spontaneous t

fission) except Sr-90 and others noted above.

d

• Where surface contamination by both alpha-and beta-gamma-emitting nuclides exists, the limits established for alpha-and beta gamma-emitting nuclides should apply independently.

6 As used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors anociated with the instrumentation.

Measurements of average contaminant should not be averaged over more than I square meter. For objects of less surface area, the average should be derived for each such object.

2 d The maximum contamination level applies to an area of not more than 100 cm,

2 The amount of removable radioactive material per 100 cm of surface area should be determined by wiping that area with dry fiher or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. ' When removable contamination on objects of less surface area is determined, the pertinent leveis should be reduced proportionally and the entire surface should be wiped.

22

t ANS 15.10 Table 5-1 (continued)

The average and maximum radiation levels associated with surface contamination resulting f

from beta gamma emitters should not exceed 0.2 mrad /hr at I cm and 1.0 mrad /hr at I cm, respectfully, measured through not more than 7 milligrams per square centimeter of total absorber.

23

,l

ANS 15.10 -

Table 5-2 Maximum Soil and Groundwater Contamination Levels [14]

a. Maximum Soil Concentration' Radionuclide Picoeuries per fram Hydrogen-3

()2 Cobalt-60 8

Strontium-90 5

Cesium-137 15

[

Plutonium-238,-239 (if found).

25 Americium-241 (if found) 30 Radium-226 5'

Radium-228 5-t (1)

If oni, one radionuclide is present, then the maximum concentration is the value listed in the table. However, if more than one radionuclide is present, determine for each radionuclide the ratio between the measured concentration (e.g., in site soil or groundwater) and the concentration listed in the appropriate table above for the specific radionuclide when.not in j

combination. The sum of such ratios may not exceed one (i.e., unity).

(2)

There is no limit for tritium (H-3) in soil.. The critical pathway is the teaching of H-3 insoil into the groundwater, which is used for drinking water. In this case, the appropriate.:

criterion is 20,000 picoeuries per liter. When H-3 use has ceased and the bulk.of H-3. waste has

- been disposed of, the Licensee should estimate the total amount of H-3 remaining on the. site,

. and a decision must be made about release of the site for unrestricted use.

D

~

' faximum Groundwater Concentration'

,_ h Picoeuries per liter

. Hydrogen 3 20,000 1

~

Cobalt-60 100

. Strontium-90 8

. Cesium-137 200' Gross alpha including radium-226 15 Radium-226, 228 5

i (1). If only one radionuclide is present, then the maximum concentration is the value listed in the table. However,if more than one radionuclide is present, determine for each; radionuclide the ratio between the rneasured concentration (e.g.,'in-situ soil or

~

. groundwater) and the concentration listed in the appropriate table' above for the specific -

~

radionuclide when not in combination. The sum of such ratios may not exceed one (i.e.,

1 unity).

(2) U.S. Environmental Protection Agency, Office of Water Supply, " National Interim Primary 24

0 0

ANS 15.10 Drinking. Water Regulations," EPA-570/9-76-003 (1976).

1 5.4 Exceptions 2

The current regulatory environment allows items with contamination or.

3 activation above those presented in 5.1,5.2, and 5.3 to be analyzed on a case'-by -

4 case basis. By petitioning the licensing or chartering agency (ies) and proving the 5

radiation dose to the public from exposure to the residual material provides no 6

unnecessary risk to the health and safety of the public the material may be i

7 released for unrestricted use. This approach can be used to leave items in place,.

8 to recycle items or for disposal in a conventional landfill as well as other 9

alternative dispositions approved by the cognizant licensing or chartering 10 agency (ies).

11 12 6.

SURVEILLANCE 13 This section presents the requirements for maintenance and surveillance that L

14 shall be implemented during storage to protect the general public and to meet the 15 various requirements of the applicable licensing or chartering agency (ies). These 16 requirements generally apply to both the SAFSTOR and ENTOMB alternatives.

17 18 All surveillance records shall be maintained as required by the licensing or 19 chartering agency (ies). The surveillance intervals specified in the following 20 sections may be increased, if warranted, based on previous surveillance results and=

21 approval by the licensing or chartering agency (ies).

22 23 6.1 Radiation Safety 25

O ANS 15.10 1

Radiation surveys of the facility shall be performed in accordance with 2

the following:

3 4

(1) Radiation surveys, including general area radiation levels, fixed 5

and loose surface contamination levels, and airborne samples shall be continued 6

on a scheduled basis. Surveys shall be performed quarterly at intervals not to 7

exceed four months. Results o: these surveys shall be reviewed by the owner's 8

radiation protection personnel. The suneys shall continue until a change in the 9

status results in the determination of unrestricted use of the facility and the site.

10 11 (2) Based upon the suney results, the requirements of the Personnel 12 Monitoring Program for personnel needing access to the facility may be relaxed in 13 accordance with the applicable licensing or chartering agency (ies) requirement.

14 Reference [2]

15 16 (3) High radiation areas where radiation dose rates equal or exceed 1 17 mSv/hr (100 mrem /hr) shall be maintained in accordance with the applicable 18 licensing or chartering agency (ies) requirements. [6]

19 20 (4) Any modifications to the facility shall be consistent with ALARA i

21 principles.

26

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ANS 15.10 1

6.2 Fire Protection

'2 It is necessary for the facility to maintain a Fire Protection Program -

3 during the surveillance period.

a

^

4-5 (1) Emergency Plan sections addressing. fire brigades, fire fighting,_

't 6

etc., shall be revised to reflect both the storage status of the facility and the 7

personnel available.

8 9

(2). Inspection and testing.of fire detection systems and fire fighting.

l l

10 equipment shall be performed in accordance with the facility's Fire Protection '

11 Program.

a 12 13 (3) : Periodic scheduled inspection tours of the accessible portions of 14 the facility shall be conducted in accordance with the facility's Fire Protection 15 Program.

16 17 -

(4) If the facility'is not to be patrolled by security personnel, the fire 18 '

detection / alarm system shall provide continuous monitoring of the facility, using.

-19 audible and visible alarms at a manned central monitoring station.

1 L20' q

?21 6.3 Physical Security 27

-1 j

O O

etNS 15.10 1

Physical security encompasses all those actions necessary to isolate the 2-public from the radioactive materials remaining at the facility:

f

.i 3

4 (1) Physical barriers (fences, locks, building walls, welded doors, etc.)

5 shall prevent access by unauthorized personnel to areas of the facility where 6

radiation dose rates exceed the permissible levels for unrestricted areas. Physical 7

barriers shall be inspected for degradation quarterly at intervals not to exceed 8

four months. A written report of each inspection shall be on file.

9 10 (2) Testing of intrusion alarm systems shall be conducted quarterly at 11

-intervals not to exceed four months. Written procedures shall be used, and the-1 12 results of the tests shall be reviewed and filed at the facility.

13 14-6.4 Structural Integrity 15 Buildings or structures containing neutron-activated or contaminated 16 -

systems shall be maintained such that the structure continues to act as a physical 17 barrier preventing public access.

18 I

19 Inspection of facility structural members, walls, floors and roofs shall -

20 be performed.' Inspections should be conducted semi-annually at intervals not to :

21=

exceed seven and one-half'monthsc These inspections shall be coriducted using '

~

.22 written instructions, and the results shall be on file.

1 er

(a')

( ')

a ANS 15.10 1

6.5 Environmental 51onitoring 2

Environmental radiation surveys should be performed periodically 3

commensurate with the nature of the facility. A program for soil, vegetation, and 4

water sampling should be considered that provides for comparison with any 5

previous environmental history.

6 7

The surveys shall be conducted using written instructions, and the 8

results shall be on file. Any increase in radiation levels shall be investigated for 9

cause and effect. Significant changes shall be reported to the cognizant licensing 10 or chartering agency (ies).

11 12 7.

ENVIRON 51 ENTAL, ASSESSNIENT 13 The planning for decommissioning shall include an environmental assessment 14 of decommissioning activities. The assessment shall address the regulatory 15 requirements, emironmental impact factors, and the methods for evaluation of 16 impacts.

17 18 7.1 Regulatory Requirements 19 The licensing or chartering agency (ies) may prepare an environmental 20 assessment to determine whether an impact statement or a finding of "no 21 significant impact" is required. The responsible agency (ies) may require the 22 owner to submit environmental information for preparing an environmental 29 e

y y

p.

1 L)

( )

ANS 15.10 The following section describes the information that should be 1

assessment.

2 provided by the owner.6 3

4 7.2 Ensironmental Impact Information 5

The factors that should be considered in evaluating the environmental 6

impacts of decommissioning a research reactor are:

7 (1)

Purpose and need for the action 8

(2)

Decommissioning alternatives, including the proposed action 9

(3)

Affected environment 10 (4)

Environmental consequences 11

a. direct effects 12

b. indirect effects 13

c. possible conflicts with governmental land use actions 14

d. environmental effects of alternatives 15

e. energy requirements 1E

f. natural and depletable resource requirements 17

g. urban quality, historic and cultural resources 18

h. mitigation of adverse environmental impacts 6 ror U.S. reactors, the National Environmental Policy Act (NEPA) of 1969 as amended, Title 1. scetion 102.

19 20 applies t research react r dec mmissi nmg. Regulations for implementation are pronded in Reference 131 31 Section 1501.4 of Reference [3] requires the responsible rederal agency to determine whether an environmental 2]

impact statement is required.

23 24 ror licensed research reactors, the U.S. Nuclear Regulatory Commission (NRC) is the responsible rederal agency.

25 NRC procedures for implementing NEPA regulations are provided in Reference [13).

26 27 ror rederai and miiitary research reactors.nnous rederal agencies, such as the U.S. Department of Energy gg (doe) and the Department of Defense (DoD) are responsible.

30

~

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.O ANS 15.10 1

The research reactor owner should provide this information to the 2

responsible agency with the Decommissioning Plan. Certain factors may not apply 3

on a site-specific basis and may be eliminated or modified.'

4 5

8.

QUALITY ASSURANCE 6

A Quality Assurance Program complying with American National Standard 7

Quality Assurance Program Requirements for Research Reactors, ANSI /ANS f

8 15.8 shall be prepared for the decommissioning operation. [4] The program shall 9

cover the systems, structures and components and other activities related to health 10 and safety of the public, workers, and the environment that are involved in the 11 selected decommissioning alternative, 12 i

13 Each alternative contains activities that are common to all alternatives such-14 as:

15 (1)

Preparation, safety review, and control of plans, specifications, and -

16 procedures to be used in the decommissioning 2

17 (2)

Personnel and environmental monitoring 18 (3)

Monitoring.of any' materials to be. released for unrestricted use 19 (4)

Characterization, packaging, and' disposal of radioactive material 20 (5)

Site termination survey -

21 4

i

.7 Turther discussion of these factors is included in Appendix C.

73 I

31

if E

(s

(

-%)

Q ANS 15.10 1

The selected decommissioning alternatives will introduce activities 2

requiring special emphasis with respect to the quality assurance program.

3 4

8.1 SAFSTOR 5

For the SAFSTOR alternative the quality assurance program shall 6

address:

7 (1)

Monitoring and reporting (to regulatory agencies) of 8

facility radiation levels and environmental radiological -

'9 conditions.

10 (2)

Maintenance of radiological and environmental' 11 monitoring equipment.

12 (3)

Surveillance, maintenance (and testing, if possible) of 13 the fire protection system.

14_

(4)

Surveillance, maintenance and testing of the security.

15 system.

16 17 8.2 ENTOMB 18 -

In addition to the items listed under SAFSTOR,' the ENTOMB 19

- alternative quality assurance requirements shall address:

20

-(1)

The materials, fabrication and installation of the 21 entombment

. boundary.

22 (2)

The inspection and maintenance / repair of the 23

_ entombment boundary integrity throughout its design 32

O O

.j ANS 15.10 1

1

~1 lifetime.

2 3-83 DECON 4

In addition to the items listed under SAFSTOR, the DECON

.5 alternative quality assurance requirements shall address:

6 7

(1)

The monitoring of equipn'ent important to safety to be 8

used in the decommissioning activities. This equipment should 9

include such items as cranes, lifting slings, temporary 10 walkways, liquid filtration equipment, and temporary t

11 portable ventilation equipment (e.g. HEPA filters).

12 (2)

The monitoring of materials used in the construction 13 of equipment or structures related~to health and safety.

14 of the public, workers, and the environment used in 15 support of decommissioning activities.

16 17 Necessary modification to the quality-related activities governed by 18-the facility's Technical Specifications (or equivalent) shall be made by appropriate.

19 changes to the specifications.

20-t 21 9.

- REPORTS / DOCUMENTATION 22 Information that supports the facility decommissioning should be' collected 23 throughout the facility's lifetime Unless required data is collected and archived,.

33

Ug

.O-ANS 15.10 1

the difficulty and cost of decommissioning are significantly increased. This section 2

identifies applicable data for archiving which is developed during the several l

r 3

phases of the facility's life.

4 5

9.1 Design / Construction 6

The following design / construction documentation should be 7

collected and archived:

8 (1)

Complete as-built drawings 9

(2)

Construction photographs with detailed captions 10 (3)

Procurement records that identify types and quantities 11 of materials used during construction-12 (4)

Equipment / components specifications, including.

13 pertinent information, i.e., supplier, weight,-size, materials of 14 construction, etc.

15 9.2 Operations 16 The following documentation should be collected and archived 17 during the operational phase of the facility:

18 (1)

Safety Analysis Report (s) 19 (2)

Technical Manual (s) 20 (3)

Emironmental~ Assessments J

-21 (4)

Power History

~

22 (5)

Radiological Survey Reports 23 (6)

Operating and Maintenance Procedures 1

/m b--

U i

i ANS 15.10 i

l'-

(7)-

' Abnormal Occurrence Reports t

2 (8)

Deactivation Plans / Reports 3.

(9)

Technical Specifications 4-(10)

Design Changes and Updated Drawings 5.

9.3 Decommissioning

.6 The following documentation should be collected and archived to 7

provide a detailed record of the decommissioning:

8 Planning Phase o

9 (1)

Environmental Assessment 10 (2)

Environmental Impact Statement (if needed) 11 (3)

Decommissioning Plan 12 (4)

Activity Specifications 13 (5)

Project Management Plan 14 (6)

Funding Plan 15 (7)

' Cost and Schedule Estimates 16 17 Dismantlement and Restoration Phase I

18 (1).

Detailed Work Procedures 19 (2)

Safety Analysis Report (s) 20 (3)

Periodic Status Reports 21

(.4)

Final Site Survey Report 22

'(5)

Final Program Report 23 (6)

License Modification / Termination 35.

~

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ANS 15.10 I

2 10.

REFERENCES 3

[1]

W.J. MANION, T.S. LAGUARDIA, " Decommissioning Handbook,"

4 DOE /EV/102128-1, U.S. Department of Energy, November 1980.

5 Nuclear Energy Services, Inc., Danbury, Connecticut.

6

[2]

Code of Federal Regulations, Title 10, " Energy," Part 20.202, 7

" Personnel Monitoring," Government Printing Office, Washington 8

D.C.

9

[3]

Code of Federal Regulations, Title 40, " Protection of Environment,"

10 Parts 1500-1508," Council on Environmental Quality," Government 11 Printing Office, Washington, D.C.

12

[4]

American National Standard Quality Assurance Program 13 Requirements for Research Reactors, N402-1976 (ANS-15.8),

14 American Nuclear Society, La Grange Park, IL.

15

[5]

Code of Federal Regulations, Title 10, " Energy," Part 20.105, q

16

" Permissible Levels of Radiation In Unrestricted Areas,"

17 Government Printing Office, Washington D.C.

18

[6]

Code of Federal Regulations, Title 10, " Energy" Part 20.203, 19

" Caution Signs, Labels, Signals and Controls." Government Printing 20 Office, Washington, D.C.

21

[7]

G.J. KONZEK et al.," Technology, Safety and Costs of-1 22' Decommissioning Reference Nuclear Research Reactor,"-

]

23 NUREG/CR-1756, March 1982.

q 36 a

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.1 ANS 15.10 1

[8]

U.S. Nuclear Regulatory Commission, " Assuring the Availability of 2

Funds for Decommissioning Nuclear Reactors," Regulatory Guide l

3 1.159, August 1990.

4 5-

[9]

U.S. Nuclear Regulatory vommission," Termination of Operating 6

Licenses for Nuclear Reactors," Regulatory Guide 1.86, June,' 1974.

7 8

[10]

Code of Federal Regulations, Title 10, " Energy," Part 50.75, 9

" Reporting and Recordkeeping for Decommissioning Planning,"

10 Government Printing _ Office, Washington, D.C.

11 12 (11]

Code of Federal Regulations, Title-10," Energy," Part 50.33 (k),

13

" Contents of Applications; General Information," Government 14 Printing Office, Washington, DC.

15 16

[12]

U.S. Nuclear Regulatory Commission, Standardization and.Special 17 Projects Branch,'" Guidance and Discussion of Requirements for an 18 Application to Terminate a Non-Power Reactor Facility Operating -

19 License," Revision 1, September 15,1984.

20 21

[13]

Code of Federal Regulations, Title 10," Energy," Parts'51," Licensing 22 and Regulatory Policy and Procedure for Environmental Protection."

23 Government Printing Office, Washington,' DC.

-24 37:

ANS 15.10 i

1

[14]

Federal Register," Order Establishing Criteria and Schedule for I

2 Decommissioning the Bloomsburg Site," Volume 57, Number 34, 3

Pages 6136-6141, Government Printing Office, Washington, DC, 4

February 20, 5

1992.

6 7

1

.i 8

Only the standards explicitly referred to in this document qualify as 9

reference. Subsequent revisions of these standards shall not be used.

l 10 t

9 I

i I

6 9

s 1

g v

w

?

ANS 15.10 q

1 2

Appendix A 3

3 4(This Appendix is not a part of American National Standard for Decommissioning of.

5Research Reactors, ANSI /ANS-15.10-1993, but is included for information~ purposes 6only.)

7 8

Terminology for Decommissioning Alternatives j

9 10The terminology used to. identify decommissioning alternatives for nuclear facilities is l

11 varied. The relationship of the various terms to those of Regulatory Guide 1.86, 1

112" Termination of Operating Licenses for Nuclear Reactors,"is summarized below.

13

~'

14 15

• Source Term Relationship to Reg. Guide 1.86 16 Terminology"*-

171

'18NUREG/CR-0130 [1]

Dismantlement Removal and Dismantling i

19 Safe Storage-hardened No Equivalent a

20 Safe Storage passive

- No Equivalent 21 Safe Storage-custodial

' Mothballing

. 22 Entombment Same 1

23 j

24NUREG/CR-0278 [2]

Layaway Mothballing _

25 Protective Storage

. No Equivalent

.26 Entombment

. Same -

27-

. Dismantlement Removal and Dismantling-28 29AIF/NESP-009

[3]

Mothballing Same l

30 Entombment Same.

l 31

_ Prompt Removal / Dismantling-Removal and Dismantling 32 Delayed Removal / Dismantling No Equivalent 33 341AEA-179

[4]

_ Stage 1 Mothballing-

' Stage 2 No Equivalent '

j 36-Stage 3 Removal and Dismantling j

37-

38NUREG/0590

'[9]

SAFSTOR" -

Mothballing 1

39' ENTOMB" Entombment 40 DECON"

' Removal and Dismantling -

1 41 l

142*-

See Reference for Appendices A and C j

' 43"

10 CFR 50.82 provides for completion of decommissioning without significant. delay -

44:

.unless delay is necessary to protect public health and safety :

45*"

4 A fourth alternative, conversion, isl discussed in Regulatory Guide 1.86, but is not.

1 39 N

e 9

Q s

ANS 15.10 1 applicable to research reactors 3

i, i

l 40 1

-1 j

~

O O

ANS 15.10 1

Appendix B 2

3(This Appendix is not a part of American National Standard for Decommissioning of Research 4 Reactors, ANSI /ANS-15.10-1993, but is included for information purposes only.)

5-6 Activity Specification Format 7

'881. Purpose 9

10 Summary of what is to be accomplished 11 12B2. Activity Plan 13 14 Brief description of how this task is to be accomplished and how it relates to the Reactor 15 Decommissioning Plan 16 17B3. Criteria 18 19 Special conditions to be met before and during the performance of this task 20 21 A.

Engineering, Scheduling, Technical Requirements 22 23 (1) Reference or discuss any special engineering studies conducted in support of this 24 task 25 (2) Describe the required operating condition and availability of facility systems and 26 equipment 27 (3) List any special equipment which must be designed, procured, or purchased 28 (4) Discuss any additional engineering studies needed, relative to this task 29 (5) Identify any special work requiring subcontracts (e.g. moving heavy equipment, 30 demolition, restoration) 31 (6) List any special permits required for this task (e.g. Department of Transportation 32 (DOT) shipping) 33 34 B.

Health, Safety and Environmental Protection 35 36-Describe any special radiological and industrial safety requirements. Include special-37 protective clothing or equipment, and possible releases to the environs.

38 ri 39.

C.

Standards -

L

-40 L List any special codes, regulations, etc. (other than those referenced in B3.B) which 42 apply.

Discuss quality control, inspection of work, etc.

43 L

41 I

J

.i

e n

V.

\\

t i

ANS 15.10

1 Appendix B (continued) 2 3

4B4. Procedures and Sequence of Events 5

6 Discuss the work involved in this task, describing major steps and providing a sequence of 1

7 events. Detailed steps are not required; however, identify where detailed procedures are 8

required, a

9 h

I t

5

.[

i

. A l

s l

- 1 i

-1 42'

s,

~

O O

ANS 15.10 1

Appendix C 2

3(This Appendix is not a part of American National Standard for Decommissioning of Research.

4 Reactors. ANSI /ANS-15.10-1993, but is included for information purposes only.)

5 6

7 Discussion of Environmental Impact Factors 8

9C1. Environmental Impact Factors 10 11 Each environmental impact factor identified in 40 CFR 1502 (10]* and the information 12 required to define the factor are presented below.

13' 14C1.1 Purpose and Need for Action 15 16 Describe why the research reactor is being decommissioned, including any historical 17 background pertinent to the need to decommission.

18 19C1.2 Decommissioning Alternatives Including the Proposed Action 20_

21 Describe the decommissioning alternatives considered (SAFSTOR, ENTOMB or 22DECON) and include the selected decommissioning method and the reasons for-23 rejecting the other alternatives. The reasons should be in comparative 24 form to provide a clear basis for the selected alternative.

25 26C1.3 Affected Environment 27 28-Briefly describe the research reactor, the associated facilities, and the areas affected by 29 decommissioning.

30 31C1.4 Environmental Consequences 32:

33 Describe the scientific and analytic base used in selecting the proposed decommissioning.

34 alternative. A listing of the potential environmental factors that should be discussed is 35 shown i_n Table C-1. The discussion should include (as applicable): the environmental 36-impacts (beneficial and adverse) of the various decommissioning alternatives, the 37 relationship between the shor't-term uses and the maintenance and enhancement.of long-

38 term productivity of the environment, and any irreversible or irretrievable _ commitments 39 of resources should the proposed alternative be implemented.'

- _40 41

• See References for Appendices A and C 43

3 O

n m

ANS 15.10

'1 Table C-1 2

3 List of Environmental Factors 4

5

1. Direct EITects 6

7 A.. Occupational Radiation Dose 8

B. Public Radiation Dose 9

C. Commitment of Land 10 D. Liquid, Gaseous, Solid Discharges 11 E. Aesthetics 12 F.

Noise 13 14

2. - Indirect Effects 15 16 A. Licensed Disposal Site Use 17 B. Local Landfill Use-18 C. Public Radiation Dose from Transportation 19 D. Socio-Economic Effects 20 1.

Housing -

21 2.

Employment 22 E. Public Road Use 23 24 3.

Possible Conflicts with Government Actions 25 26 A. Federal 27 B. Regional 28 C. State 29 D. Local 30 31 4.

Environmental EITects of Alternatives 32-33 A. SAFSTOR-34 B. ENTOMB

.35 C. DECON

-.36 37 5.

Energy Requirements 38 i

39 A.' Electricity 40 B. Fuel Oil 41 C. Gasoline 42 D. Diesel -

43 E. Natural Gas

~44 45 --

44

,t.

e g

.p O,,

d ANS 15.10' I

'6.

Natural and Depletable Resource Requirements 2

3

.A.

Concrete 4

B. Wood -

5 C. Metals 6

D. Gases (argon, nitrogen, acetylene, helium, oxygen) 7 E. Water 8

F.

Land 9

G. Chemicals (decontamination) 10 11 7.

Urban Quality, Historic and Cultural Resources 12 13 A. Noise 14 B. Public Road Use 15 C. Socio-Economic Effects 16 D. Aesthetics 17 18 8.

Mitigation of Adverse Environmental Impacts 19' 20 A. Shielding 21 B. Filtration, Evaporation and Demineralization of Water-Based Liquids 22 C. Dilution 23 24 j

25C2. Estimation of Environmental Impacts 26 27 Estimates of the_ major potential environmental impacts may be developed using the 28 methods identified in the following subsections. Those impacts that are deemed 29 insignificant should be discussed only briefly.

30 31C2.1 Occupational Radiation Dose 32

-33 Decommissioning of a research reactor results in radiation exp'osure to workers. There 34 are two sources of radiation dose: 1) external exposure to radioactive materials; and 2)-

-35~

internal exposure to inhaled' gases, particulates,;and aerosols. External exposure results 36' from the decommissioning activities, including decontamination ~ and removal of-

'37 radioactive components and transportation of radioactive wastes for disposal.

38

-39 Estimates of external doses from decommissioning activities can be made from surveys'ofL 40

. radiation dose rates throughout the buildings and estimates of the working population?

41.

dose commitment for the various activities. Estimates of occupational transportation 42l dose (e.g., truck driver) may be obtained by the methods provided in WASH-1238. [5]

t 43 Estimates of internal dose may be made by the methods of ICRP Publications. [6]

44_

Estimates of contaminated concrete dust release rates may be obtained from 45

NUREG/CR-0130. [1]

45

o o

ANS 15.10 1C2.2 Public Radiation Dose 2

3 Decommissioning activities may expose the public to radiation from: 1) gaseous and 4

aerosol emissions; 2) liquid releases; 3) radioactive material transportation; and 4) direct 5

exposure at the site.

6 7

Estimates of the sources, concentrations and release rates of gaseous and liquid -

8 emissions to the environment are available in NUREG/CR-0130 [1] and AIF-NESP-009.

9

[3] Public radiation doses including results from postulated accidents are summarized in' 10 NUREG/CR-0672. [7] Estimates of transportation dose may be made by the methods of 11 WASH-1238. [5] The external dose at the site may be estimated by calculation, or by 12 measuring the dose rate at the site boundary and assuming an individual is at that -

13 location for the duration of decommissioning activities (or until all radioactive material is l

14 removed).

15 16C2.3 Nonradioactive Ef11uents 17 18 The release of nonradioactive liquid, gaseous, and particulate effluents should be 19 evaluated for their chemical toxicity and nuisance impacts. Chemical toxicity is site 20 specific and must be evaluated on a case-by-case basis. Liquid and gaseous chemical 21 discharge source concentrations and rates should be estimated to determine the impact 22 on the area soils, water supplies, and atmosphere. Noncontaminated dust levels from 23 concrete demolition by blasting may be estimated by the methods of BNWL-1697. [8]

24 25C2.4 Commitment of Resources 26 27 Throughout the decommissioning program, resources are consumed to achieve the 28 desired decommissioning condition. The major resources consumed should be identified.

29 i

46

0 k

ANS 15.10

.1 Appendix D 2

3 (This Appendix is not a part of American National Standard for Decommissioning of 4

Research Reactors, ANSI /ANS-15.10-1993, but is included for informational purposes only.)

5 6

7 List of Decommissioned Research Reactors 8

9 As a resource in preparing for decommissioning activities, a list of research reactors 10 which have been or are in the process of being decommissioned is provided. NRC-licensed 11 reactors in the process of decommissioning at the time this standard was prepared include 12 the f ollowing:

13 14 15 Docket No. and Reactor Thermal 12> cation 16 Power 17-i 18 50-47 Watertown Arsenal, U.S. Army (Pool Type) 5 MW Watertown, MA 19 20 50-54 Cintichem (Pool Type) 5_ MW Tuxedo, NY 21 22 50-72 University of Utah 5

W Salt Lake City, UT 23 24 50-77 Catholic University (AGN-201) 0.1 W Washington, DC 25 26 50-139 University of Washington,(Argonaut) 100 kW Seattle, WA 27 28 50-142 University of California,(Argonaut) 100 kW Los Angeles, CA 29 30 50-148 University of Kansas (Pool) 10 kW Lawrence, KS 31 32 50-185 NASA Mockup (Pool Type) 100 kW Sandusky, OH 33 i

34 50-192 University of Texas (TRIGA Mark II)

'250 kW Austin, TX 35

.I 36L 50-262 Brigham Young 10 W

Provo, UT.

~

-37 47

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e O

O ANS 15.10 1

NRC-licensed reactors which have been decommissioned and had their license 2

terminated include the following:

3 4

Docket No. and Reactor Thermal Location Date License 5

Power was 6 Terminated 7

8 50-1 Illinois Inst, of Technology 100 kW -

Chicago, IL 04-28-72 9

(Water Boiler Research) 10 11 50-4 USN Research Lab (Pool Type) l' 'MW Washington, DC. 03-18-71 12 13 50-6 Battelle Memorial Institute (Pool Type) 2 MW Columbus, OH 12-22 87.

14

'15 50-8 N.C. State (Aqueous Homogeneous) 100 W Raleigh, NC 09-07-66'

r 16 17 50-17 Industrial Reactor Labs. (Pool Type) 5 MW Plainsboro, NJ 11-04-77 18 19 50-43 U.S. Naval Post-Graduate School (AGN-201) 0.1 W

Montery, CA 2010-11-72 21 22 50-50 North American Aviation 5

W Canoga Park, CA 06-30-58 23 (L-47 Homogeneous) 24 25 50-58 Oklahoma State University (AGN-201) 0.1

-W Stillwater, OK 2603-19-74 27-28 50-60 U.S. Navy Hospital (AGN-201M) 5-W Bethesda, MD 06-24 -

'29 30 50-64 University of Akron (AGN-201) 0.1 W Akron, OH 10-09-67 31

-32 50-84 University of California (AGN-201) 0.1 W Berkeley, CA 08-23-66.

33 34 50-87 Westinghouse Training Reactor 10 kW-Zion, IL ;

.10-27-88' 35 36-50-94 Rockwell International (L-77) 10 W Canoga Park, CA 02-11-821 j

-37 38 50-98 University of Delaware (AGN-201) 0.1 W

Newark,' DE -

02 26-79 39.

40-50-99 B&W Lynchburg (Pool) 1.0 MW Lynchburg, VA 4107-20-82 42 43 50-101' Gulf United Nuclear (Pawling Lattice 100 W Pawling, NY-06-25-74 44 Test Rig) 45 5

48'

~

9 p

t) v ANS 15.10 1

50-106 Oregon State (ANG-201) 0.1 W Corvallis, OR 11-10-81 2

3 50-111 N.C. State (Pool) 10 kW Raleigh, NC 01-13-83 4

5 6

50-112 University,f Oklahoma (AGN-211) 100 W Norman, OK 02 14-90 7

8 50-114 William March Rice University (AGN-211) 15 W

Houston, TX '

909-26-67 10 11 50-122 University of Wyoming (L-77) 10 W

Laramie, WY 1212-05-75 13 14 50-124 Virginia Tech (Pool) 100 kW Blacksburg, VR 08-11-88

-15 16 50-129 West Virginia (AGN-211 P) 75 W Morgantown, WV 09-07-84 17 18 50-135 Walter Reed Medical Center 50 kW Washington, DC 07-26-72 19 (L-54, Homogeneous Solution) 20 21 50-141 Stanford University (Pool Type) 10 kW Stanford, CA 06-21-83 ~

22 23 50-147 Rockwell international 200 W Canoga Park, CA 10-01-80 24 25 50-167 Lockheed (Pool Type) 10 W

Dawson Co., GA 2609-01-60 27 28 50-187 Northrop 1 MW Hawthorne, CA 06-29-86 29 30 50-172 Lockheed (Radiation Effects Reactor) 3 MW Dawson Co., GA 08-31-71 31 32 50-202 University of Nevada (L-77) 10 W Reno, NV 02-24-75

~33 34

.50-212 General Dynamics (Fast Critical Assembly) 500 W San Diego, CA' 03-05-65 35 36 50-216 Polytechnic Institute, NY (AGN 201M) 0.1 W Bronx, NY 12-21-77 37 38~

.50-224 University of California, Berkeley (Pool) 1 MW Berkeley, CA '

03 08-91 39 40 50-227 General Atomic Co. (TRIGA Mark III) 1.5 MW San Diego, CA 12-10-75.

41 42 50-235 Gulf General Atomic (APFA) 500 W San Diego,' CA 10-22 69 43.

44 50-240 Gulf General Atomic (HTGR) 100 W San Diego, CA 04-02-73 :

-45 49-

'nU O.-

L l'

ANS 15.10 1

50-253 Gulf Oil Corp. (APFA III) 500 W San Diego, CA 08-10 2 3

50-267 Georgia Tech.

0.1 W Atlenta, GA 01-07 86 4

5 50-294 Michigan State (Triga Mark 1) 250 kW East Lansing, MI (M-05-90 6

~

7 50-310 NUMEC and Commonwealth of PA (Pool) 1 MW Ouehanna, PA 12 02-66 8

9 50 375 Rockwell International (L-85) -

3 kW Canoga Park, CA 04-08 87 10 11 50-394 California Polytechnic (AGN-201) 0.1 W San Luis' Obispo, CA 19 85 12 13 50-433 University of California (L-77) 10 W Santa Barbara, CA 11-17-89 14 15 50-406 Tuskegee (AGN-201) 0.1.W

' Tuskegee, AL -

11-02-84 16

+

- 17.

50-538 Memphis State University 0.1 W Memphis, TN 10 19-88 18 19 20 Numerous DOE Reactors have been shutdown or placed in a state of indefinite stand-by.

21-When applying this standard to DOE reactors,it may be helpful to refer to the following list 22 of reactors officially shut down and decommissioned or shutdown and destined to be 23 decommissioned: [11]

24 25 Los Alamos Water Boiler 26 Chicago Pile Number 5 27

Zero Power Reactor 6 28-Zero Power Reactor 9 29

. Loss of Fluid Test 30 Power Burst Facility 31 Thermal Test Reactor Number 1 32 Puerto Rico Nuclear Center 33' B Production Reactor

-34<

C Production Reactor 35 PNL Plutonium Recycle Critical Facility

!36 n

i l

l i

50

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O d

w v

- ANS 15.10 i~

1 References for Appendices 2

3

[1]

R.I. SMITH, et al., " Technology, Safety and Costs of Decommissioning a Reference 4

Pressurized Water Reactor Power Station," NUREG/CR-0130, June 1978.

5

[2]

" Technology, Safety and Costs of Decommissioning a Reference Nuclear Fuel 6

Reprocessing Plant," NUREG-0278, Vol. I and Vol. 2 l

i 7

[3]

W.J. MANION and T.S. LAGD".DIA,"An Engineering Evaluation of Nuclear

.8 Power Reactor Decommissioning Alternatives," AIF-NESP-009. Atomic Industrial 9

Forum, Inc. November 1976.

10

[4]

" Decommissioning of Nuclear Facilities," IAEA-179-1975. International Atomic l

11 Energy Agency, Vienna, Austria.

12

[5]

• Environmental Survey tf Transportation of Radioactive Materials to and from i

13 Nuclear Power Plants," U.S. Atomic Energy Commission, WASH-1238, December l

14 1972.

i 15

[6]

" Limits for Intakes of Radionuclides by Workers," ICRP Publication 30, Annals of 16 the International Commission on Radiation Units and Measurements, Vol. 2, Nos, j

17 3,4,1979 (Part 1); Vol. 4, Nos. 3,4,1980 (Part 2); and Vol. 5, Nos.1-6,1981 18 (Supplement to Part 2). Pergamon Press, Oxford, England and New York, N.Y.

19

[7]

H.D. OAK, et al., " Technology, Safety and Costs of Decommissioning a Reference 20 Boiling Water Reactor Power Station," NUREG/CR-0672, Vol.1, June 1980.

21

[8]

J.M. SELBY, et al., Considerations in the Assessment of the Consequences of 22 Effluences from Mixed Oxide Fuel Fabrication Plants," BNWL-1697, Revision 1, pp.

23 78-79. Battelle Pacific North-west Laboratories, Richland, Washington, June 1975.

24

.[9]

Code of Federal Regulations, Title 10, " Energy," Part 50.82, " Application for n

51

4

/~

U ANS' 15.10 1

Termination of License," Government Printing Office, Washington, D.C.

2

{10]

Code of Federal Regulations, Title 40," Protection of Environment," Part 1502, 3

Government Printing Office, Washington, DC.

4

[11]

" Organizations Responsible for Department of Energy Owned Reactors," Attachment 5

1 of DOE 5480.6, September 23,1986.

6 52

O O

ANS 15.10 Foreword (This forward was prepared to provide a background and explain the need for non-power reactor standards and criteria concerning the use of those standards.)

The American Nuclear Society Standards Secretariat established Subcommittee ANS-15 in the fall of 1970 with the task of preparing a standard for the operation of research reactors. In January 1972, this charter was expanded to the multiple tasks of preparing all standards for research reactors. To implement this enlarged responsibility, a number of subcommittee working groups were established to develop standards for consideration, and complementary action by Subcommittee ANS-15. ANS-15.10 is one of these groups.

1 In March 1979, Working Group ANS-15.10 was assigned the task of developing a draft standard for decommissioning of research reactors.

Since that time changes in regulatory policy were incorporated into t

this current revision. The ANS-15.10 Working Group membership at the time of completion of the standard was:

M.H. Voth, Chairman, Pennsylvania State University JJ. Adler, TLG Engineering, Inc.

W.E. Austin, Westinghouse Electric Corporation J.A. Christian, Chem-Nuclear Environmental Sersices, Inc.

T.S. LaGuardia, TLG Engineering, Inc.

M. Mendonca, U.S. Nuclear Regulatory Commission T.R. Schmidt, Sandia National Laboratory l

Present decommissioning regulations for reactors are contained in the Code of Federal Regulations, Title 10, " Energy," Part 50," Licensing of Production and Utilization Facilities," which addresses primarily the financial qualifications of the applicants. The policy for licensed power reactors is contained in U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide 1.86," Termination of Operating Licenses for Nuclear Reactors," which was issued in June 1974 and is generally used as a basis for decommissioning activity. Currently, the NRC is in.

the process of developing more specific criteria on decommissioning in an effort to generate a more explicit overall policy. This standard provides needed procedures, criteria, and standardization for the

)

~

decommissioning of research reactors which is also appropriate for test reactors.

l J