ML20138P045
| ML20138P045 | |
| Person / Time | |
|---|---|
| Issue date: | 12/31/1985 |
| From: | NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | |
| References | |
| RTR-REGGD-3.065, TASK-CE-304-4, TASK-RE REGGD-03.XXX, REGGD-3.XXX, NUDOCS 8512240264 | |
| Download: ML20138P045 (21) | |
Text
- _
U.S. NUCLEAR REGULATORY COMMISSION December 1985
/
M 0FFICE OF NUCLEAR REGULATORY RESEARCH Division 3 3" %
g D
g, 4 [)y!
j Task CE 304-4 kh %
DRAFT REGULATORY GUIDE Afl0 VAL'JE/ IMPACT STATEMENT
Contact:
C.R. Mattsen (301)443-7661 4
't.
STANDARD FORMAT AND CONTENT.0F '
Jr DECOMMISSIONING PLANS FOR 10 CFR PARTS 30, 40, AND 7J. LICENSEES i
m 4
+
4 s
4 0512240264 851231 PDR R'GGD 03.XXX R PDR Thil regulatory galde and the alloCisted value/ impact Statement are being iltued in draf t form (0 iPvolve the putIlC In the early StaJet of the developmeet of a regulatory position je thlt area. They have flot retelved Complete sta f f review 481 do not represent an of f t(14140C staf f pctition.
PubliC Corrent5 are being tollCited on both draf L5, the guide (locluding any implementation $Chedule) and the value/ tarat t State *ent.
CoFPentl on the value/impaf t Statement thould tse a(Companied t'y tupp9f ting data. Welt ten Co meett ma y tie te7ulatory r ariission, Washington, OC MMS. Cowent s
$wbmittei to the Rules and Prote14res 9tanch, C'8 8, ADf t, U.S. Ac t ear o
ed y a I 53 to deIlvered to 9009 4 W), 'taryland hat ter.al Bank Buildin1,17 35 Old r.corgetown poad, tet hesda, "4r,14a1 f rom 2:15 a.m. to 5:00 p.s.
(cptes of townts received ma y te essaired at the PSC Putlic N<wwnt poem,1717 H 5treet Nd.,
washington, cc. Co ents tii be anst *einfui if re< eived by February 17, 1986.
Beauests for single Copies of draf t gaides (which may be reproduced) or for placement on an automatf C distributton ligt for sing!e copies of future draf t guides in spe<lfic divisions should be apde in wetting to the U.$. huclear sejulatory Coentsston, Wash 6citon. M 20555. Attention: Olrector, Division of Techaltal Informa tion an1 Doc ument Control.
TABLE OF CONTENTS Page INTRODUCTION 1
Chapter 1.
GENERAL INFORMATION 5
1.1 Name, Address, and License Number...
5
- 1. 2 Organizational Responsibilities and Authority 5
- 1. 3 Historical Information 5
6 1.4 Training..
- 1. 5 Procedures 6
- 1. 6 Contractor Assistance.
6 1.7 Safeguards.
6
- 1. 8 Activities, Tasks, and Schedules 7
1.8.1 Activities and Tasks........
7 1.8.2 Description 7
1.8.3 Schedules 7
- 1. 9 Quality Assurance.
7 Chapter 2.
RADIATION PROTECTION 8
2.1 Administrative 8
2.1.1 ALARA Policy 8
2.1.2 Radiation Work Permits 8
2.1.3 Contractor Personnel 8
2.2 Methods for Ensuring Radiation Safety.
8 2.2.1 Radiation Protection Equipment 8
2.2.2 Ventilation 9
2.2.3 Work Area Air Sampling 9
2.2.4 Radioactive Waste Management 9
Chapter 3.
FINAL RADIATION SURVEY PLAN 10 Chapter 4.
FUNDING.
11 REFERENCES.
12 DRAFT VALUE/ IMPACT STATEMENT.
13 APPENDIX, Form NRC-314 17 l
6 111
D INTRODUCTION Section 30.36, " Expiration and Termination of Licenses," of 10 CFR Part 30,
" Rules of General Applicability to Domestic Licensing of Byproduct Material";
Section 40.42, " Expiration and Termination of Licenses," of 10 CFR Part 40,
" Domestic Licensing of Source Material"; and Section 70.38, " Expiration and Termination of Licenses," of 10 CFR Part 70, " Domestic Licensing of Special Nuclear Material," require, in part, all holders of specific licenses to submit a completed Form NRC-314 when they decide to terminate the license.
(A copy of Form NRC-314 is provided in the appendix.) In addition, certain licensees must submit a plan for decontamination.
On February 11, 1985, the Commission published proposed amendments to its regulations, including 10 CFR Parts 30, 40, and 70, (50 FR 5600) concerning specific criteria for decommissioning nuclear facilities.
Amended Sec-tions 30.36, 40.42, and 70.38 would require certain licensees to submit, on or before the license expiration date, a plan for completing decommissioning when the licensee decides to terminate the license.
A decommissioning plan should be submitted if decommissioning activities could significantly increase the potential health and safety impact on workers or the public and have not been previously approved by NRC.
For instance, large manufacturers under Part 30, uranium hexafluoride production under Part 40, and processing and fuel fabrication under Part 70 would be included under this requirement.
In some cases, licenses presently contain a specific condition that requires submittal of a decommissioning plan.
Any information collection activities mentioned in this draft regulatory guide are contained as requirements in 10 CFR Parts 30, 40, and 70, which provide the regulatory basis for this guide.
The information collection requirements in 10 CFR Parts 30, 40, and 70 have been cleared under 0MB Clear-ance Nos. 3150-0017, 3150-0020, and 3150-0009, respectively.
l 1
1.
Purpose and Applicability This draft regulatory guide, developed in conjunction with the proposed decommissioning rule, would be applicable when a licensee decides to permanently discontinue all licensed activities involving nuclear materials.
The purpose of the guide is to identify the information needed by the NRC staff for evalua-tions involving decommissioning.
The guide also provides a format for submit-ting this information.
Conformance with this guide is not required, but its use will facilitate preparation of a decommissioning plan by licensees and timely, uniform review by the NRC staff.
A different format will be acceptable to the staff if it provides an adequate basis for approval of a decommissioning plan.
Submittal of a decommissioning plan would be required promptly after the end of operational activities and prior to the expiration date of the license.
However, since the proposed decommissioning rule would require approval of a decommissioning plan before starting decommissioning procedures and review and approval may take several weeks, it is recommended that the plan be prepared and submitted as soon as residual radioactive contamination has been assessed.
If the information requested in such' sections as 1. 4, 1. 5, 1. 7, 2.1, and 2.2 is the same as or similar to information currently required, only changes need to be submitted.
Information contained in previous submittals, statements, or reports filed under the license may be incorporated by reference, provided the referer.ce is clear and specific.
However, some cases may occur (e.g., Sec-tion 1.5 and paragraph 2.2.4) in which a license amendment may be required to effect a change.
It is recommended that the licensee consult with the NRC staff when preparing a decommissioning plan.
2.
Graphic Presentations Graphic presentations such as drawings, maps, diagrams, sketches, and tables should be employed where the information may be presented more adequately or conveniently by such means.
Due concern should be taken to ensure that all information so presented is legible, that symbols are defined, and that scales are not reduced to the extent that visual aids are necessary to interpret per-tinent items of information.
These graphic presentations should be located in the section where they are primarily discussed.
2 i
References used should appear either as footnotes to the page where dis-cussed or at the end of each chapter.
3.
Physical Specifications a.
Paper size (1) Text pages:
8-1/2 x 11 inches.
(2) Drawings and graphics:
8-1/2 x 11 inches; however, a larger size is acceptable provided the finished copy whtn folded does not exceed 8-1/2 x 11 inches.
b.
Paper stock and ink.
Suitable quality in substance, paper color, and ink density for handling and reproduction by microfilming or image-copying equipment.
c.
Page margins.
A margin of no less than 1 inch should be maintained on the top, bottom, and binding side of all pages submitted.
d.
Printing (1) Composition:
text pages should be single spaced.
(2) Typed face and style:
should be suitable for microfilming or image-copying equipment.
(3) Reproduction:
may be mechanically or photographically reproduced.
All pages of text should be printed on both sides and the image printed head to head.
e.
Binding.
Pages should be punched for standard 3-hole loose-leaf binders.
f.
Page numbering.
Pages should be numbered with the digits correspond-ing to the chapter followed by a hyphen and a sequential number, e.g.,
the third page of Chapter 4 should be numbered 4-3.
Do not number the entire report sequentially.
3
g.
Table of contents.
A table of contents and an index of key items should be included.
4.
Procedures for Updating or Revising Pages Data and text should be updated or revised by replacing pages.
The changed or revised portian on each page should be highlighted by a " change indicator" mark consisting of a bold vertical line drawn in the margin opposite the binding margin.
The line should be of the same length as the portion actually changed.
All pages submitted to update, revise, or add pages to the report should show the date of change and change or amendment number.
A guide page listing the pages to be inserted and the pages to be removed should accompany the revised pages. When major changes or additions are made, a revised table of contents should be provided.
4
n f
Chapter 1.
GENERAL INFORMATION A discussion of planned decommissioning activities should be presented in this chapter.
Plans describing the organization, schedules, and activities for accomplishing decommissioning should be submitted.
1.1 Name, Address, and License Number The licensee's name and the appropriate numbers of the licenses to be ter-minated shcul'd be furnished.
1.2 Crganizational Responsibilities and Authority Positions with responsibilities related to decommissioning safety should be identified and their functions described.
The minimum qualifications for these positions should be presented.
}
- 1. 3 Historical Information The licensee should desciibe historical information on operational occur-rences that could adversely affect decommissioning safety.
Such things as spills, releases, or >ther accidents that resulted in significant residual radioactive contamination should be included.
The licensee should also de-scribe system and equipment design, including modification or revision, in high-radiation areas and for locations of normally inaccessible systems and equipment that may be contaminated, and any areas of the site that may be excessively contaminated.
This type of information can be obtained from plant records and personnel familiar with the plant operations.
This information is important to safety and should be considered when preparing plans for decom-missioning (see paragraph 1.8.2).
(The proposed decommissioning rule would require that this type of information be kept in a file; see proposed Sections 30.34(i), 40.41(g), and 70.32(1). )
l 5
1.4 Training A description of the training program for operators, contractor personnel, and other personnel should be presented.
This section should also contain a description of the system for maintaining records of trained personnel.
1 1.5 Procedures The licensee should state a commitment to conduct decommissioning activities and tasks
- in accordance with approved written procedures.
The control system that ensures that written procedures are prepared, reviewed, revised, approved, and implemented should be described.
- 1. 6 Contractor Assistance The licensee may choose to accomplish some or all decommissioning activities and tasks by using contractors.
However, the responsibility for safety during decommissioning rests with the licensee, and all license requirements will be followed by a contractor.
For each contract, the scope of work, administrative controls to be used to ensure adequate health and safety protection, and the relationship of the contracted work to the schedule for other activities should be described.
- 1. 7 Safeguards If applicable, a description of and a schedule for any proposed changes to the NRC-approved security plan and special nuclear material and accounting plan should ba provided in this section.
If not applicable, a notation to this effect should be entered in this section.
- For purposes of this guide, an activity is an organized unit of work for per-forming a function and may consist of several tasks.
A task is a specific work assignment or job.
6
1.8 Activities, Tasks, and Schedules l
1.8.1 Activities and Tasks In this section, the licensee should list or tabulate major activities and tasks related to processes, systems, and equipment to be decommissieled.
Ref-erences 1, 2, and 3 contain information that may be helpful in developing a list of decommissioning activities and tasks.
1.8.2 Description A description and an analysis of the proposed methods for accomplishing the activities and tasks listed in paragraph 1.8.1 should be presented.
The description should include a discussion of historical information on operational occurrences that could adversely affect decommissioning safety (see Section 1.3),
the current assessment of residual radioactive contamination, and potential accidents that could have a significant impact on decommissioning safety.
The analyses should show that decommissioning can be accomplished in a safe manner.
- 1. 8. 3 Spedules For major activities, the relationship between activities and tasks should be shown.
The schedules for accomplishing interrelated activities and tasks should be presented.
Schedules or diagrams should clearly indicate the esti-mated time for completion of decommissioning.
1.9 Quality Assurance The licensee should describe the quality assurance (QA) program to be established and executed during decommissioning.
Equipment (e.g., measurement instruments, shielding) and procedures that will be subject to QA should be listed.
The QA program should be established at the earliest practical time consistent with the schedule for accomplishing an activity or task.
Where some portion of the QA program has not been established at the time the decommission-ing plan is submitted, the description should include a schedule for implemen-tation.
The management positions responsible for review and audit should be specified.
7
Chapter 2.
RADIATION PROTECTION A description of the methods used to ensure protection of workers and the environment against radiation hazards during decommissioning should be presented in this chapter.
The licensee should include both administrative and technical issues in the descriptions.
2.1 Administrative 2.1.1 ALARA Policy The policy for keeping occupational radiation exposure and radioactivity in effluents at low as is reasonably achievable (ALARA) should be described.
The description should explain how this policy will be implemented.
2.1.2 Radiation Work Permits The criteria for issuing and terminating radiation work permits should be j
described.
2.1. 3 Contractor Personnel The licensee should describe radiation protection policies to be applied to contractor personnel safety when they are working in restricted areas and the means of implementing them.
2.2 Mothods for Ensuring _ Radiation Saf ety 2.2.1 Radiation Protection Equipment The types of instruments to be used for measuring radioactivity should be identified.
The purpose (e.g., personnel monitoring, radiation surveys), range, and sensitivity should be described for each type.
The anticipated use of respiratory protection should be explained.
Methods for contamination control (e.g., anticontamination clothing, control of access to ree,tricted areas) thould be described.
8
2.2.2 Ventilation Ventilation systems to be'used for containment of airborne radioactive con-tamination should be described.
The description should include anticipated use of special and temporary ventilation systems.
2.2.3 Work Area Air Sampling The program for determining airborne radioactivity in work areas should be described.
The description should include locations of air samplers, types of equipment, and frequency of sampling and analyses.
2.2.4 Radioactive Waste Management Processes and systems to be used for handling, storing, and disposing of radioactive waste should be described.
If radioactive wastes are to be tempo-rarily stored on site, the storage methods should be explained.
If wastes from restricted areas are to be disposed of by land fill or similar methods, the I
means for demonstrating that criteria for release f or unrestricted use are met should be specified (see % 20.302 of 10 CFR Part 20).
9
Chapter 3.
FINAL RADIATION SURVEY PLAN In this chapter, the licensee should describe the plan for demonstrating that the plant, site, premises, and the contiguous adjacent environs if appro-priate will meet criteria for release for unrestricted use.
The final radiation survey plan should include (1) the proposed method for ensuring that sufficient data and all equipment, systems, structures, and site are included in the survey (diagrams, plot plans, and layout drawings should be used to facilitate presen-tation), (2) a description of and data on background radiation, (3) the type, specifications, and operating conditions of instruments to be used, and (4) methods to be used for reviewing, analyzing, and auditing data.
The final radiation survey plan should demonstrate that a reasonable effort has been made to eliminate residual radioactive contamination.
It should be designed so that results and interpretations can be verified by the NRC inspection staff.
10
Chapter 4.
FUNDING In this chapter, the licensee should show how adequate funds for the com-pietion of decommissioning will be made available.
A cost estimate based on the status at the time license termination is requested should be submitted.
A comparison of this cost estimate with present funds should be provided, if there is a deficit in present funding, the licensee should include a description of how sufficient funds for decommissioning will be made available.
l
,q f
11
l REFERENCES 1.
H. K. Elder and D. E. Blahnik, " Technology, Safety, and Costs of Decommissioning a Reference Uranium Fuel Fabrication Plant," prepared for the Nuclear Regulatory Commission (NRC) by Pacific Northwest Laboratory (PNL), NUF:EG/CR-1266, October 1980.
- 2.
E. S. Murphy, " Technology, Safety, and Costs of Decommissioning Reference Non-Fucl-Cycle Nuclear Facilities," prepared for the NRC by PNL, NUREG/CR-1754, February 1981.*
3.
H. K. Elder, " Technology, Safety, and Costs of Decommissioning a Reference Uranium Hexafluoride Conversion Plant," prepared for the NRC by PNL, NUREG/CR-1757, September 1981.*
- Referenced NUf:EG-series reports are available, under the decommissioning document file number 4' FR 10370, for inspection and copying for a fee at the Commission's Public Documer,t Room, 1711 H Street, frd.. Washington, DC.
NUREG series reports are available for purchase from the National fechnical Information Service, Springficid, VA 22101.
12
\\
ORAFT VAlUE/ IMPACT STATEMENT 1.
PROPOSED ACTION 1.1 Cescription i
Fe'ruary 11, 1985), the in a recent Federal Register notice (50 FR 5600, o
Commission announced its intentions to revise its regulations regarding decom-missioning.
An important aspect of the proposed rule changes would require, among other things, that certain licensees submit plans for completing decommis-sioning.
This proposed action is the publication of guidance that describes the information needed in and a format for a plan for completing decommissioning (decommissioning plan) submitted by 10 CFR Parts 30, 40, and 70 licensees.
- 1. 2 Need At the present time there is no published NRC guidance that provides the informition needed in decommissioning plans.
Specific guidance should be pro-vided ty NRC so th t licensees can prepare and submit this information with a minimum of time and effort.
The purpose of this proposed action is to publish guidance that describes the kind of information that is needed in a decommis-sioning plan, it also presents a format for these plans that will facilitate staff review.
1.3 Value/impac t 1.3.1 P1RC l
The proposed quidance would facilitate licensing review and reduce corre-spondenct with applicants and licensees. Minor additional impact on NRC re-sources is anticipated since similar plans are currently reviewed by the staff.
- 1. 3. 2 Other Government Agencies No other governuent agency is directly involved unless the agency is an NRC applicant or licensee.
If the agency is an NRC licensee, the value/ impact will be similar to that for industry presented in Section 1.3.3 of this analysis.
13
\\
1.3.3 Industey Industry should benefit from the guidance provided by this action because the guidance would facilitate preoaration and submittal of a decommiss:oning plan.
No significant additional economic impact is anticipated as a result of the proposed action.
This regulatory guide merely provides guidance for pro-cedures and plans that would be required by the proposed regulations or are currently required.
- 1. 3. 4 Public No significant incremental impact on the public is foreseen as a result of this action.
2.
TECHNICAL APPROAC61 The guidance is nontechnical in its content; thus this section is not applicable.
1.
PPOCEDURAL APPROACli 2.1 Procedural Alternatives Potential NRC procedures that may be used to promulgate the information that would be contained in the guide are:
Regulation Policy statement NUREG-series report Regulatory guide Branch technical position A policy statement or a regulation is not suitable for incorporating the degree of detail that will be reflected in this guide.
A branch technical posi-tion (BTP) is sometimes prepared for specific quidince, However, no OfP is being develo?ed on this subject.
BIPs have limited circulation and are con-sidered to be temporary measures to be useri only until a more formal mode of guidance can be issued; over the long term, a BTP would not adequately fill the 14
l need in this case.
A NUREG-series report is convenient means for providing informat.on.
However, a NUREG-series report usually contains only results of specific studies and is not appropriate for this action.
A regulatory guide is the preferred course of action.
4.
STATUTORY CONSIDERATIONS 4.1 NRC Authority This action would fall under the authority of the NRC as defined in the Atomic Er;rgy Act of 1954, as amended, and the Energy Reorganizatien Act of 1974, as amended, and is implemented through the Commission's regulations in Title 10 of the Code of Federal Regulations, as cited in the introduction to this guide.
6 4.2 Need for NEPA Assessment Issuance or amendment of guides for the implementation of regulations in this chapter of the Code of federal Regulations is a categorical exclusion under paragraph 51.22(c)(16) of 10 CFR Part 51.
Thus, no environmental impact state-ment or assessment is required for this action.
5.
CONCLUSION A draft regulatory guide should be prepared and published for comment.
)
I 15
i 1
APPENDIX Form NRC-314 I
17
l mIRC Ferne 314 U S. NUCLE AH REGUL ATORY COMVISSION APP'<ov t u a v ows nisp J t bo nus 10t>H Al hedlM.wl 10 ( D r4 mi 4h f S14.et w n " "'" ' ""
CERTIFICATE OF DISPOSITION OF MATERIALS (A!! ireres stLIST be corrt>Iete d, piense pernt) uct %st t Naut AND AM*t sa L it e Nst NovatM Let t Nht E kPf M A f id)N O A f t THE LICE NSE E GR ANY INOlVIDU AL E XECUTING THrs CE H fiflCATE ON BEHALF OF THE LICENSE E CE R'IFIES THAT /Cha-4 e#or tnere the stwave.are ornst twice I
.. ~ _
A MA f E RIALS D A T A IChr e av nf (aryHere, as reessav A 1 NO M ATE RI ALS H AV E EV E R M EN POSSE SSE D OH PHOLURf D (4Y THE LICE NSE E UNDE R THIS LerENSE OR 2 AL L M AT E RI AL S PROCU R E D AM.) OR POSSE SSE D U V THE LtCENsEE UND( H THE LICENSE NUMME H CITED ABOVE H AVE BE EN TR ANSF E RHE D ON part to W m'C M M A 5 N**C L i( t N M NLW6t M OR
) AL L M A TE R, ALS F He > CURE D AND CH POSSE SSE D B Y THE LICENSE E UNDE R THE LICE NSE NtIV8E R CITED AdOv t HAN E BE E N TH ANST E RRED ON u.,,
,~
],ssuto ev tot ifatt OF em a. >... A > uv ue v ve.
AN AGRE EVE N T ST A TE PURSU AN T TO SE CT 6ON 214 Of THE ATOUtC E NE RGY AC T OF 198 4. AS AVE NDE D AND THE E NE RGY MEvRG ANilATION 2
04 ACT Of 1914 4 U A T[ H e AL S ** A v l B F I N D r$ POLE D DS IN THE F OL LOWING MINNE FI (Orm r.be smri t d<a w prwerbres - er ehr rwwt sam e is riea ert use rev revero* o' f
'~
We erw n, tw pm, me area smen y r
~
B O T Hf R l' A I A 1 OUR LICE Nh H [kOT V E T E n Ptht D PL E SE TE RVIk f f 'If
~
~ '
~'
^
~~" ~~
~
2 W AS A R ADI AT ON 5Up w E Y CONDUCT E D TO CONilHM THf A%I NCE OF L it F NLL D R ADIO ACTIVf MAi( HI ALS AND TO DE T E RMINE WHE THE R ANY
_ CON T AM'N Afif;N RE MAIN $ ON T HE PRI Mi$E S COVE N E D BY fut LICE N'J P /t'hm a one/
NO V E S. T HE RE SU L f 5 (CA. a o,wr AkE Ati ACHI D OR A E RE FOR A ARD[ Q TO NRC ON (Derej 3 THE Pt H50N TO RE COf4T ACfi O HE G AMuiNG THE INf 0RV All',N PHelvli DI;N l'ISf0HM
~
~ ~ ~ ~ ~ ~ " - ~
H N"Wf f t L 6.
.#e E NuYel H 4 U AIL All E U I V4E CD58Hl W)'sL I NCE f'I G A H!)i% IHl$ L tCI N',6 70 HE TUHN TO (I R flF YING Of f tCI AL
- ~
f
(.RfCf09 DivrLioN ist f ut L C rct [ ANO V A f E su AL %Af E f Y Of f tCE Of N'ICL F AH V A Tf RI AL SAf f iY ANI) SAf f f,U ARUS U 5 NIJCE I Aft Pf GUL A TOH r Cr NYU,104 gg
- AsHw, ton OC m,s NHC f eem.714 (ll RJI 19
UNITED STATES
,,,,,ct,,,,,,,
NUCLEAR REGULATORY COMMISSION cossaae e viis raio WASHINGTON. D.C. 20555 o f,'2"o' c rE RMIY 8so G 4F OFFICIAL BUS NESS PEN ALTY FOR PRIV ATE USE SW US
'FC 1 IGPISalE2 170S'30'421' A0v-r:V 0; IIDC COCU"E'.T C O *. T ' O L D E M - fa E C C l HI*GTON CC PCE55 e