ML20153H110

Requests Comments on Encl Advance Notice of Proposed Rulemaking 10CFR76 Re Regulation of U Enrichment Facilities

ML20153H110
Person / Time
Issue date:	04/27/1988
From:	Clark A NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	Bewley H, Dressel R, Zekall J E.I. DU PONT DE NEMOURS & CO., INC., MARTIN MARIETTA ENERGY SYSTEMS, INC., PENNSYLVANIA, COMMONWEALTH OF
References
REF-PROJ-M-48 NUDOCS 8805120129
Download: ML20153H110 (10)

Text

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l APR 2 71988 I

To Addressees:

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1

SUBJECT:

ADVANCE NOTICE OF PROPOSED RULEMAKING:

i PROPOSED NEW 10 CFR 76, REGULATION OF URANIUM ENRICHMENT FACILITIES l

2 I have enclosed a copy of a Federal Register Notice issued by the U.S. Nuclear t

Regulatory related to the regulation of uranium enrichment facilities, i

.The Commission is interested in receiving comments on the information f

proposed in the Notice or on any aspects of uranium enrichment regulation.

Thank you very much for your assistance and your interest.

f Sincerely, l'

opgccu.t.Ec :I.V rY:

E THOMAS CLARK;'JR.

A. Thomas Clark, Jr.

Advanced Fuel and Special Facilities Section Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety e

Enclosure:

As Stated l

cn Attached list Distribution:

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<r Control Enginsering Mr. H. Dale Bewley Exnon Chsmical Americas Martin-Marietta ES P.O. Box 400 P.O. Box K Baytown. Texas 77522-O'00 55 Jefferson Center Oak Ridge. TN 37831 Mr. R. J. Dressel Mr. John Zekall Engineering Department State of New York E. 1. duPontde Nemours 5 Company. Inc.

Public Service Commission P. O. Box 6090 Department of Public Service Newark. DE 19714-6090 Three Empire State Plaza Albany. NY 12223 Hoechst Celonese Corporation Dr. William J. Hall ATIN:

Mr. Steve Camp Professor of Civil Engineering 1101 17th Street University of Illinois Suite 307 Urbana, Illinois Washington DC 20036 Dr. Thomas Carmody Center for Chemical Processing Safety Dr. James E. Beavers American Institute of Chemical Engineers Martin Marietta Energy Systems. Inc.

345 E 47th Street P.O. Box Y New York. NY 10017 Building 9733-4 Oak Ridge. TN 37831 Mr. Yim Gee Mr. Robert Heine California Public Utilities Commission E. I. duPontde Nemours & Company. Inc.

505 Van Ness Avenue 1701 Pennsylvania Avenue. S.W.

San Francisco. CA 9;102 Suite 900 Washington. DC 20006

[

t Mr. Mort Mullins Mr. William Concoran Director of Regulatory Affairs Allied-Signal Corporation Monsanto Corporatien 1001 Pennsylvania Avenue 1101 17th Street. N.W.

Washington. De 20004 Suite 60; Washington. Dc 20036 Mr. Joseph Caporossi Mr. Stanley J. Schechter Manager. Health and Safety Rohn and Haas American Cyanamid Corporation Engineering Divirion 1 Cyanamid Plaza P.O. Box 554 Wayne. SJ 07470 Bristol. PA 19007

Mr. 888hsca 6kaehds i

Bishop, Cook, Purcell & Reynolds 1400 L Strcet, N.W.

W:shingten. DC 20005-3502 Mr. James Behrend Office of Operations and Facility Reliability NE 33 U.S. Department of Energy Washington, DC 20545 Mr. Joseph DeStefano URENCO, Inc.

Suite 610 2600 Virginia Ave., N.W.

Washington, DC 20037 Mr. James C. Hall Assistant Manager for Enrichment Operations U.S. Department of Energy Oak Ridge Operations Office P.O. Box E Oak Ridge, TN 37831 Mr. B. J. Reckman c/o Fluortech, Inc.

MS B3J 3333 Michelson Drive Irvine, CA 92730 Mr. Kyle Olsen Chemical Manufacturer's Association 2501 M Street, N.W.

Washington, DC 20037 Ms. Cheryl Pellarin Washington Technology 1953 Gallows Road Suite 130 Vienna, VA 22180 Mr. Dennis 5. Milewski Martin Marietta Energy Systems P. O. Box P Bldg. K1550W MS 223 Oak Ridge TN 37830

{

13278 Proposed Rules rdai

• Vol. 53. No. r8 l

Inday, Apnl 22. 1988 This secton of the FEDERAL REGISTER at: the NRC Public Document Room, restructunns would be a federally contaes notees to the putAc of the 1717 H Street NW., Washington. DC chartered ennchment corporation.

P'00Cd '8S"ance of nns and

,o, py,7mn,,,,,gargow cowTAcyt which might be subject to regulation by regulatons The purpose of thew not<es A. Thomas Clark,lr Office of Nuclear the U.S. Nuclear Regulatory t

M7 En*,',y;,

Material Safety and Safeguards U.S.

Commission.The NRC staff has also

?

maxng pnor to the adopt,on of the final Nuclear Regulatory Commission, been meeting w:th some pnvate ru6es.

Washmston, DC 20555, telephone (301) companies, all of which are espressing 492-0697, an interest in engaging in uranium e) t on. "

i 8 " " *"' #0""A

• NUCLEAR REGULATORY COMMISSION

Background

This advance notice of proposed 10 CFR Part 76 A uranium enrichment facility is a rulemaking is being published to provide production facility as defined by section the public, the Department. and the Regulation of Uranlum Enrichment 11(v) of the Atomic Eriergy Act of1954, prospective regulated industry an Facaties as amended. The regulations which opportunity to provide adsice and.

currently govern the Commission's recommendations to the Commission on Aotacy: Nuclear Regulatory review and evaluation of an application the subject of uranium ennchment Commission.

for a production facility are contained in licensing.The NRC staff has developed AcTM)M: Advance r.otice of proposed 10 CFR Part 50. Part 50 provides no guidance, provided below, which wowld rulemaking.

specific guidance for licensing uranium form the foundation for a new rule,if ennchment facilities, The NRC staff has initiated. Because rulemaking may take suasesAmy:The Nuclear Regulatory never received an application for a several > ears, and applications for Commission (NRC)is considenng the uranium ennchment f acility, The staff, pnvate enrichment might be imminent, addition of new regulations Title to however, has licensed facilities w hich the NRC staff will proceed with the (Part 76) for uranium ennchment ptr.se uranium bexafluonde, which is review of applications and issuance of facilities. ne construction and thw pnncipal chemical form of uranium appropriate licenses and permits, on the operation of such facilities currently used in the gaseous diffusion process basis of the current regulations in to would be hcensed pursuant to the and the centnfuge process, the current CFR Dart 50 and the guidelmes Commission a regulations in to CFR Part methods used to produce ennched contained in this advance notice subject 50 for other production and utilization

uranium, to any revisions which might be facilities, such as nuclear power plants.

llowever, other methods for enriching appropriate based on comments In this notice, the Commisalon presents uranium can be and are being received.

Its current analysis of the applicability developed. For example, for several As noted above, current regulations of the eusting regulatiors,in 10 CFR years the Department of Energy has already provide a framework for the Part 50, to uranium ennchment facilities fostered the development of an Atomic bcensing renew of production facihties.

and poses questions for the purpose of Vapor Laser Isotope Separation (AVLIS) The initiation of a rulemaking to more ehcttmg comments on whether a process for ennching uranium. The closely define the substance of NRC separate set of regulations for uranium commercial use of these methods would review should not hold up the als be subject to regulation by the processing to completion of submitted eneral$es Cnte ia resented Commission.

applications.

The in this notice may be proposed for On Apn17,196& the Department of Wanium Hesafluoride and Pubb.c codification in the new regulation. These Energy (the Department or DOE) llealth and Safety of Uranium cntena may also be modified, dependtng pubhshed a notice in the Federal Enrichment on comments recris ed in response to Register (51 FR 11811) requestmg this notice, and upon further staff expressions of interest for participation Although the regulation of uranium analysis.

in the Department's uranium enrichment ennchment facihties could include any DAfts:The comment period expires on program. In addition, on February 17, type of technically feasible ennchment July 21,1988 Comments received after 1%7. the Department submitted a report process, as a practical matter the tw o this date will be considered if it is to the Congress on the pnvattration of predominant techniques, gaseous pra tical to do so, but assurance of DOE's utaruum ennchment enterpnse.

diffusion and gaseous centnfugation, consideration cannot be gn en escept as The report was prepared in response to ennch the uranium utthring thz chemical to comments recen ed on or before this issues raised in Conference Report H.R.

form of uranium hexafluonde. The date-94-1005 (House joint Resolution 738 pnntipal reason for using this form is ADemtssts: Mad comments. to: The Continums Appropnation,1987).The that the compound is a gas at Secretary of the Commission U.S.

letter transmittma the report indicated reasonable temperatures erd pressures.

Nuclear Regulator) Commission, that a more specific recommendation The release of uranium hexafluoride Washington, DC 20555. Attention:

would be made by the Department at from process equipment is a more Docketmg and Sersice Branch.

the end of March on the restructunns of severe chemical (tosicological) hazard De/ner comments to:11555 Rockulle the ennchment enterpnse. On March 31, than a radiation (radiological) haraid as P'ke lOne White Flint North! Rockulle, 1987, the Department provided further discussed below, MD, between 7.30 a.m. and 415 p m.

detatls on the proposed restructunng.

If uranium hesafluoride is releasei to Esamme copies of comments recened The pnncipal coinponent of the the atmosphere it will react i

-J Federal Register / Vol. 53, No. 78 / Frid:y, April 22, 1988 / Proposed P alas 13377 enothermally with motsture in the air to ne etaff considers that an intake of 50 46. 5047,50.M mm %55a.

produce hydtogen fluoride (IF) and about 9 mg of urardum is the level at

io 00. 50 61. 50 02. 50N. 5012, 5013.

uranyl Duoride (UOI.). Both whlch slight transient kidney injury is and 50.109 compounda c4n be touc. Hydrogen expected to occur, and an intske of Appendicee A. C. E G. H.1, J. K f. M.

fluende is a c.orrosive sasd upor which about 40 ess of uranium La a reasonable N. O Q and R.

can severeJy damage tisaus, upeciauy mmete of the threshold lewl at which

2. Sections not applicable for reasona the moist tissue of the Lumps ifinhaled in permatent kidney damage may begin to othn than 1:

sumcaerst concentretiana. It uran)1 occur (see NUREG-1140p nerefore, for fluonda is inhaled cw ingested, it can design purposes the staff is considertng

smw, cause internd injury to the kidneya and the calculated manmum amount that an m3 gag,,i sufficient quanuues can be lethal adult at or bebond the controued site

,,.w..

In order to demonstrate that the boundary could inhale, as a result of son stmms.nd chemical hazard of uranium credible accidents of low probability to amkemm %

bessf!voride reaction products far be in the range of 9 to 40 mg. Facilities Appenda o Pmm4 esceeds that ofits radiation. hazard one designed such that meumum efrects ApA F Raerumwa %

might consider the following example would not exceed this range should not Apowa P seserne related to just one of the reaction have a significant adverse effect on the B. Those Sections of M CIR Port 30 products, uranyl fluoride,if a person health and safety of the public, it'hich APP ) CoIMP Hel)-

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I de inhaled sufficient uranyl fluoride, as a For exposure to tF. levels which result of being exposed to a plume from cause permanent injury are not clearfy

1. Sections related to admirdstrative released uranium hexaGuoride (enriched defined. Exposure to IF at a pnxedures: Secten Et through 50.10, to six percent U-235). auch that there concentration of 100 mg/m 8 is 50.12,5313,50.20 through 232,50.3eb, in was a 50/50 chance of survidng (50 estimated to be tmbearable for on*

50.37 through 240,50.41,50.42. Sa45, percent lethahty) the chemicauy toxic minute. }{F at 13 mg/m 8 would be 50 50 through 50.53,5036. E58, 250, d

effects, that person would receive only detectable by smeu and cause possible 50fa 5015. 50 80 through 50110 except Id about 15 rem comrrutted (Itfetime) total irntation. Above 28 mg/m 8,IF would 50.100.

body dose equivalent or about the caue irritation and pvesible health

1. Appendix B' e

maxtman amount a radiation worker effects.: nerefore, the stafi considers can rece$ve in one calendar quarter (3 that 26 mg/m : IF is the maximum C. Dose Seccons of 10 CTR / bit 84.

rees) 0treiously, even further chemical concentration that a person at ce beyond it hich App /y Partially 4p intury could be rustained by the same the controlled site boundary could be

1. Pamsmphs (g) and (i) of I 5436 de Iq f

inbrideal from the hydrogen fluoride exposed for short periods, as a result of n I apply: au other paragraphs appPy.,

he produced during the same release of credible inctdents oflow probability,

2. Section SaSa refers to informattaes arantum bemafluonde.

Ennchment facilitif s designed to limit release to a value below this requested by the Attomey General for

= St.adarda RnM on anference concentration will not have a antitrust restew, Paragrapb (c)is te mects a gnificant adverse effect on the health reserved. Paragrep a (a). (b), and (d) eet s

Based on the above dtsettssion the and safety of the pub!tc.

apply orJy to nuclear power reactors.

Paragraph (e) applice to a uranhm.

staff will be guided mainly by the Analysis of the AppW of it CR ent'. Ament appucation.

chemicaleffects of reaction products Part se to Uraniumi Enrirbmaat i Sdon 50 R Contents of s

from uraniura hexafluonde in its outlook an design for the protect on of the health The NRC staff has resiewed each Applications; technical information."

es and safaty of the public.The Atomic section of to CFR Part 50 to determine applies in part to a uranium enrichmen' Tastgy Act provides authanty for the w htch sections do not apply, which plant.The extent to which paragraphs I Commission to consider any sectioria wtD apply,includtng the nature 150 34 apply is discussed below-cresequence to the pubhc health and of thed applicatxbty, and those which safety usherent in the physical will apply La part.This analysis la based A. Peregrcph fol. Preliminary Scfety charactenatica of licensed source or on the staff a judgment as to technical Analysis herort special nuclear material such as and procedural apphcabtbry. The ne fdlowing paragraphs pertain ure:uum hexafluonde.ne staff herein analysia la tntended to form a basis for principauy to nuclear power plants. (1).

proposes teforence values to be used for the NRC skalf's approach to bcensing of (3)( ). (4) (10). and (11). Replacement tbs evaluation of sites and designs wtth uranrum ennchment facthttes.

paragraphs related directly to the intent aa aa A. Dose Sections o 10 CIR Port 50 of these paragraphs should be prepared

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, g It'hich Do Not App y unless they are only apphcable to propoud refemace salaecIor UO.F.

1. Sect ons and appendices related nuciear power plants.

3 and ify, ba sed on chemical toucity, are I

atedned to be comparable with the only to nacLear reactor licenemg:

B. Paragraph fb). fino/ Screty Acolyris utal

' antenalintent of the reacier atfine Sectione SaS4a. M3Ra. M43,50 44.

Report cmens in 10 CFR Part 100. Le., a w hole-ne fdowing parageaphs pertain h4 radiation dose guideltne value i cop,,, ewyec.n e m., in pw. d ten pnncipaUy to nuclear power planta:(1).

s hied at the ist where it is behevei the serenatare d Docmawew t4 Gonmmem Pna'we Oira P o Ines oat washmem oc (2)(i). (4). (e)(v). (6)(sli), and 19).

' te:

notchni y observable threshold

%'* pose:egm to occur. ne staff thusC

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ces b P"

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esmg quenttt'ee or Rey i aua save.4 v A nst A copre e.**

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' assaentraton valaea which are at the a euem sa pWw t==c.mm uelar cones i be prepared unless they are only

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apphcable to nuclear power plants.

d a6

• beer range or average threshold level Ier themtcally toxic ef!ects whtch, if R***

weanrut sran C. Porograph (c), Physical Snunty Phn i

! d to e'aeeded, could cause tratroient or comemr.g ta pmm to L*F. ana (4. Hydwma l

Dansonent m)ury.

Newu un pe* t M te.

This paragraph apphes in its ennrety.

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.p 13278 F&l Regist:r / Vol. 53, No. 78 / Friday, April 21 1988 / Proposed Rules i

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D. Pamgwph ld), Safeguards Contingency Plan Existing Regulatory Basis for Applying Dmfl Cenem/ Design Criteriaforw Safeguards to Enrichment Facilities Umnium Enrichment This paragraph applies in its entirety.

1. Section 50.34(c) requires that each The staff has prepared draft Genere E. Paragraph (e) applies in its entirety. applicant for a license to operate a Design Criteria for uranium enrichmentu F. Paragraph (f) does not apply.

production or utilization facility must G. Paragraph (g) does not apply..

include a physical security plan as part which are intended to apply to any y

4. Section 50.35 applies, except for f their application.

technique used for that purpose. These nudear power re(ii), which refers to

2. Section 50.78 requires each holder draft General Design Criteria have been paragraph (a)(4) drawn from several sources, including -

actor siting criteria. A of a construction permit (issued under those previously proposed for other replacement paragraph related to siting Part 50)'if te9uested b the types of fuel cycle facilities and those in a

Y criteria for a uranium enrichment facility Commission, to submit installation use in to CFR Par' 50 for nucIear power should be prepared.

Information on Form N-71, permit plants. They are imended to provide

5. Section 50.36 applies in part t verification thereof by the International 8eneralguidance as to topics which -

uranium enrichment The following Atomic Energy Agency, and take such must be considered and the overall paragraphs related to nuclear power other action as may be necessary to performance objectives related to each,

plants will not apply:(c)(ly91A) and implement the US/lAEA Safeguards criterion. The actual haplementation of \\

(c)(1)(ii)(A). Paragraphs (c)(11(i)(B) and Agreement,in the manner set forth in the general design criteria will be i! 73.6 and 75.11 through 75.14, different than in the case of nuclear la s, u c u lly a 11 ply

3. Section 73.1(b)(1)[i] :tates that Part nd dP P tho '

to uranium enrichment plants.

73 prescribes mquirements for the Qp a s

de s bei Paragraph (c)(2) applies to both nuclear physical protection of production and considered and will be commensurate power plants and reprocessing plants, utilization facilities licert >d pursuant t with the safety function of the specific This paragraph could apply to uranium Part 50.

structuree, systems or components enrichment plants in the same manner

4. The material control and related to those designs. As experience, ~

as it applies to fuel reprocessing plants.

accountability requirements of I 70.51(b) is gained on the application of the All other paragraphs apply to uranium (1), (2), (5), and (6), ! 70.51(c) and cnteria, modificat.ons may be deemed ennchment except (c)(7), which is 70.51(d) pertain to enrichment facilities.

appropriate to the criteria. It is also specific to nuclear power plants.

5.The Material Control and expected that designs to implement the

6. Section 50.54,"Conditions of Accountability Reform Rule, as criteria willin most instances not be Licenses," applies in part to uranium contained in I$ 74.51,74.53, 74.55,74.57 comparable with that of nuclear power t;

enrichment. Paragraph (a) applies to and 74.59, pertains to facilities plants. In particular, the confinement iI, ;-

nuclear power plants and fuel authorized to possess five formula criteria might apply to only limited areaan h

reprocessing plants, but could be kilograms (or more) of strategic special of the plant where significant releasea.

applied to a uranium enrichment plant.

nuclear ma terial, except for reprocessin8 could occur which, in turn. could cause' The following paragraphs apply to a plants and nuclear reactors licensed exposure in excess of the reference uranium enrichment plant in their pursuant to Part 50. Thus, this rule values for toxic effects.

entirety: b c.d (1), (n), (p(), ),v(), )(x(), )(,y()e), (f), (g), (b), (1),

would apply to an enrichment facility As discussed in a previous section of

(

, (aa), and (cc). The that handles er producea bi$ enriched this notice, the current technologies, following paragraphs apply only to uranium (but not those limited to low using the chemical form uranium nuclear power plan

• 0), (m), (o), (q), (r),

enriched uranium production),

hexafluoride, would be of more (s). (t), (u, (w), (z), and (bb). Paragraphs

8. Sections 70.51,70.57, and 70.58 (in immediate aor.cern. In this section we (i.1), and (k), apply to operator licensing their entirety) pertain to any facility provide these draft criteria as based on and may or may not be applicable to uranium enrichment.

authorized to possess special nuclear the NRC staff's current considerations material to moderate strategic as to potential hazard to the health and

7. Section 50.55,"Conditions of significance, except that nuclear safety of the public. We note. in I

construction permits." applies in part to reactors licensed pursuant to Part 50 are particular, that the draft criteria uranium enridstnent. The following exempted from Il 70.57 and 70.58. Thus, presented for design for effects of paragraphs apply in their entirety to an enrichment facility that handles or natural phenomena are characterized by uranium enrichment: (a). (b), (c), and (d).

produces uranium enriched above 10 return periods. These criteria should be Paragraph (e) apidies only to nuclear used in conjunction with data provided power plants. Paragraph (f) applies to percent but less than 20 percent (in the by competent authorities which relate both nuclear power plants and fuel U-235 isotope) would be subject to design variables such as ground ll 70.51,70.57, and 70.56.

reprocessing plants (quality assurance) a acceleration and wind speed to return and could apply to a uranium Existing Sahm. 4,._ taons That do period.

enrichment plant.

not Apply to Enrichment Fadlities but

8. Section 50.57, "Issuance of Could be Applied Either by a Condition GeneralDesign Crite. ia operating license." applies in part to License r by Amending 10 CFR Part An application for a construction uranium enrichment. Paragraphs (a) and p rmit for a uranium enrichment facility (b) apply wholly. Paragraph (c) applies

1. Section 74.31 (i.e., the Low Enriched criteria for the proposed facility. These must include the principal design only to nuclear power plants.

9. Section 50.71, "Ma:ntenance of Uranium Refora Rule) contains material General Design Criteria establish records, making of reports," Paragraphs control and accountability (MC&A) minimum requirements for the principal (a) thrugh (d) apply wholly. Paragraph regulations for facilities authonzed to design criteria which are commensurate (e) applies to nuclear power plants, but possess special nuclear material oflow with their safety function. These could apply to a uranium enrichment strategic significance, but specifically General Design Criteria may not be plant.

exempts production and utilizaSon complete. Any omissions do not relies e factlities licensed pursuant to part 50.

the applicant from the requirement of

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F:d;ral Register / Vol. 53. No. 78 / Friday. April 22, 1968 / Pnposed Rules 13279 providing the necessary safety features have safety significance shall be for accessibility to the equipment of in the design of a specific facility. In protected against dynamic effects, onsite and available offsite emergeno addition to satisfying the General including effects of missiles and facilities and services such.u hospit sis.

Design Criteria the epplicent must:

discharging fluids, that may result frcm fire and police departments, ambula ce (1) Design against the loss of natural phenomena, accidents at nearby service and other emergency agene..ss.

confinement capability or other industrial, military, or transportation

. ot Normo / OP6Nilen.f or capability which would jeopardize the facilities, equipment failure, and other De8/gn Bost8[U#

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health and safe's of the public where similar events and conditions both

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such loss of capability results from any inside and outside the facility.

Design single failure in systems having safety Protection Against Fires and Explosions (a) Enrichment fades must be o b diversity in nystems Structures, systems, and components designed so that the concentration of commensurate with their safety which are determined to have safety hazardous materials at or beyond the significance must be designed and boundary of the exclusion area (1) under function:

(3) Minimize the possibility of non.

located so that they can continue to normal operating conditions. shall be as random, concurrent failures ofimportant perform their safety functions effectively low as is reasonably achievable, and (2) under credible fire and explosion as the result of design basis eccidents elements in protection systems:

exposure conditions. Non. combustible including those of low probability, shall (4) Provide design criteria and design bases for resistance of parts of the and beat resistance materials must be not create any undue nsk to the health facility to upperlimit accidents and for used wherever practical throughout the and safety of the public.

maximum probable natural phenomena facility, particularly in locationa wtal to (b) The design of the facility must be when the consequences of such events the control of hazardous materials and adequate to provide protection against endanger the health and safety of the to the maintenance of safety control severe external events that could result functions. Explosion and fire detection, in the nicase of quantities and public; alarm, and suppression systems shall be concentrations of nazardous material (5) Provide adequate protection for ernployees from hazards which could designed and provided with sufficient which may be of public heal,th and affect their performance of actions capacity and capability to minimize the safety significance.The design bases for aberse effects of fires and exploalon on such events aball take into account their required to protect the public from exposure to hazardous materials.

structures systems, and cornponents historic frequency and severity in the.

There may be some facilities for which are determined to have safety region of the site and the potentialrisk which the General Design Cnteria are significance. The design must include to public health and safety. including the not sufficient and for which additional provisions to protect against adverse inventory of hazardous materials in the criteria must be satisfied in the interest effects that might result from either the facility and the size and the proximity of of public safety. Also some of the operation or the failure of the fire the population at risk.The type of 7'

General Design Criteria may not be suppression system.

severe events to be considered will vary metwes. M. ems, ad among sites, however, earthquakes, necessary or appropriate for a specific a

facility. For facilities such as these, Components tornadoes, and floods shall be considered in all cases as described in departures from the General Design Structures systerns, and components paragraphs c. d. and e below.

Criteria must be identified and justified.

which are determined to have safety (c) Historical informa tion conceming Genem/ Requirements significance must not be shared between the regional seismicity interpreted in an enrichment facility and other Quality Standards and Records facilities unless it is shown that such light of regional structural geology and Structures, systems, and components sharing will not impair the capability of site geological conditions shall be used whien are determined to have safety the enrichment facility to perform its for determining the maximum vibratory safety functions. including the ability to ground motion which reasonably could significance shall be designed.

fabricated. erected and tested tn retum to a safe condition in ths event of be expected to affect the site during the operating hfe of the facility.Such an accordance with the quality assurance an accident.

earth uske will have a rnean return CFR Part 50. Appropriate records of the Proximity of Sites perioh of the order of 500 years.8 Design critena set forth in Appendix B to to design. fabrication, erection, and testing An enrichment facility located near earthquakes of shorter retum period of structures systems and components other nuclear facilities must be designed may be proposed, and shall be justified which are determined to have safety to ensure that the cumulative effects of through considerations of the significance must be maintained by or their combined operations will not incremental risk to public health and under the control of the licensee constitute an unreasonatie risk to the safety relative to the 500-year interval.

throughout the bfe of the facility.

health and safety of the public.

(d) Historical information conceming the regional and locat incidence and Protection Against Environmental Testing and Maintenance of Systems severity of tomadoes shall be used to Conditions and Components establish a site specific design tomado (a) Structures. systems, and Systems and components that are event.The characteristics of the design components which are determined to detennined to have safety significance have safety significance shall be must be designett to permit inspection, designed to withstand the effects of. and malatenance, and testing.

,N,%',%NN,NnIM e em cs-a v 'Temtsve Promus fx use be compstible with, the environmental g egency gpagity Development of smaic netwetens for B=wsi-Conditions associated with operation, APP ed Tnhnsosy counot ATc w t'ss h

maintenance, shutdown, inting, and Structures systems, and components Depannei of cameetaal am M which are determined to have safety (b) Structures, systems, and significance must be designed for UNDYdNNsc e

accidents.

.p components which are determined to emergencies. The design must provide u empeoed soon j l

13280 Feder:I Register / Vol. 53. No. 78 / Friday, Apnl 22, 1988 / Proposed Rules tornado shau be determined considerirrg propagating failure, or gross rupture Process Safety both the tomado frequency for the dunng the design life of the facility' region in which ee fedlity is foes ted, as Compartmentalization of process Protection S *t*

I well as the frequency of occurrence for a inventory, when used as a method of (a) Protection systems shall be tornado of a given intensity within that region.'

reduclns the amount of hazardons designed (t) to initiate action that will (e) The design ban. Dood as a material capable of being released by assure that specified ac ptable s

minimum shall be the Standard Proj,ect any single or local failure of pnmary operating design limits are not exceeded

(

Flood as defined and in common use by containment. shall be considered in as a result of operational occurrences

\\(,

the design as a means to effectively isolate and (2) to sense potentially hazardous or Proj, Corp af Engineers. The Standard ect L d is the floor resulting from and contain the process inventory in accident conditions, and to activate the most.. vere Dcod.protecton rainfall modular units or atates for all systems and components required la depth area. duration relationship and nog og g ensure the safety of operating persormel

/

isobyetal pattern of any stoms that is conditions' and the public or to give audible and visual alarm so that action can be taken considered reasonably characteristic of Ventilation Systems in a timely manner to ensure such the region in which the watershed is located. If snow melt may be Ventilation syn tems required for the safety. Systems and components shall substantial, appropriate amounts shall confinement of hazardous materials be activated automatically where this be included with the floor. producing shall be designed and apsrepriately mode is compatible with the safety f

talnfaD. When floods are predominantly tested to ensure their operabdity dunng requirements to be satisfied.

caused by snowmelt, the Standard nasal or abnormal conditions.To (b) Protection systerns shall have Project Flood shall be based on critical acmmolish this objective, these systems reliability and in situ testabiUty. The combinations of snow, temperature, and shall be dasigned to meet the following design or protection systems shad I

water losses.

requirements:

consider alternate methods at least lf) Structures, systems, and (a) The desired ventilating air flow sufficient to ensure that [t) no single components which must withstand the direction shall be maintained under failure results in loss of the protection design basis earthquake to meet the functions and (2) removal from senice operating and accident conditions.

reqotrements of paragraph (a) shall be of any component does not result in loss (b) ne ventilation system shall of the protection system such that it wiU a c mm date changes in operating operate with acceptable reliability. The el or t le a a n test conditions, such as vanauons in protection systems shall be designed to i

,g g

.I d

temperature or pressure, and shad be permit the periodic testing of their I

efeit ca capaMe of safely controDing aD om fundons whue the plant is la operauon cept d ons ted that the use of an equivalent static load gases that could be associated with to determine competency to perform method provrdes adequate n rmal or accident conditions.

their intended safety functions.

'l consen a tism.

(c) The continuity of necessary (c) Protection syste.m shall be (g) Conservative estimates of ventilation shall be assured by means of designed to fad into a safe atate or into atmospheric dispersion of hazardous alternate equipment. fall safe systems, a state demonstrated to be acceptable material based on local meteorological or other provisions.

oc some other defuaed basis if conditions shah be used to evaluate the (d) Provisions shall be made fo, conditions such as disconnection of the impact of normal operations and of testmg. during normal operstkms, all system, loss of energy or mottve power desrgn basis accidents to demonstrate component functions having safety r adverse environments are compliance with the requirements of signincance to the extent necessary to experienced.

paragraph (a).

provide reasonable assurance that they Instrumentation and Control Systems Confinement Barriers and Systexns will perform their design safety Nhement systems shall consist of Instrumentation and control systems

(

confmement barners and eqmtsment e) Ven dation systems shah be shall be provided to moniter vanables de8i ned to permit the continued and operating systems that are I

i which control agamst the release of S

hazardms materials to the ennronroent.

ccupancy of any and all areas where significant to safety over anticipated The oorfmement systemas whxt are such occupancy is required for normal ranges for normal operation, for significant to safety shall be designed to plant perations, for safe shutdon, and abnormal operation. for accident I

conditions, and for safe shutdon.

)

protect agamst the effects of accidents for mamm>= the facdity in a safe or external natural phensmena and shall shutdown condition. Their design shall These systems shau ensure adequate be fahrscated. erected, appropriately inchade pmteen ap 64 de safety of process and utility service tested, and maintained to ensure and accumulation of hazardous operations in connection with their safety function. We variabtes and prevention of abnormalleakage, rapidly materials. The design shall also permit systema that require constant the timely and safe evacuation of personnel from au areas.

surveillance and control include procers

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p,,,,,,

systems having safety significance the

?> Year saastics T. Nakra Ptosa ee (f) Ventilation systems shall be overall confmement system.

Uruvmay of Chiuso." %toncal Estrefne Wrnds dPE'9wd to CCafine lhe hatardous Confintment barriers and their for the Uruled Staiet-Atlanhc and C,atf of Meuco m& serials duriAg DorBnI operation and associated systems, and other systems

.p[

to ensure that the release of bezardous that affect the overall safety of the plant.

rem oi.: e.ame ww.s por pr.e %M g +x p.o materials in the eIDuent gases is as low Controls shall be provided to maintain l

i Aser=ws.-l v. Re,sen et e1. WRtctcn-as reasonably achievable. Such systems these variables and systems within the 4M PNLM. Och 196 to re% retem shall also be designed to retain their prestnbed operating ranges under all

% 7 y'%%Q" $ '

confinement and separation espability normal conditions. Instrumentation and team wm m sen io re,4 wyy -a to minimite releases resulting from an control systems shall be designed to fail nns a ccident condition.

into a safe state or to assume a state l

,r Federal Regist;r / Vol. 53, No. 78 / Friday, April 22. 1988 / Proposed Rules 13281 2

demonstrated to be acceptable on some electric power source or circuit. reliable (b) the equipment containing the fissile other tasis if conditions such as and timely emergency power will be material is located behind sufficient disconnection. loss of energy or motive provided to instruments. confinement baniers and shielding to reduce the power, or adverse environments are systems, utility service systems, and probability and extent of accidental expenenced.

process systems in amounts sufficient to contamination of the environment and separation of Protection Systems and aHow operations,to be shut down safely accidental radiation exposure to and to be maintamed in a safe shutdown personnelin the event of a criticality d

Control Systems condition with all safety devices accident.

Protection systems shall be separated essential to safe shutdown functioning.

or from control systems to the extent that a Ancillary Criteria for Nuclear Criticality change or failure in a control system Nuckor CriticalitySofety Safety leaves intact a protection system with Safety Margins (a) Process and storage systems shall el acceptable reliability and independence The design of process and storage be designed to ensure that no mechamsms that could cause systems shallinclude demonstrable Control Areas margins of safety for the nuclear segregation of fissile materials can be n

A control room or control areas shall criticality parameters that are present in components whose nuclear be designed to permit occupancy and commensurate with the uncertainties in criticality safety is dependent on ths actions to be taken to operate the plant the process and storage conditions, in homogeneous distribution of fissile material.

safely under normal conditions and the data and methods used in under abnormal or accident cunditions calculations, and in the natee of the (b) Components whose nuclear to either operate the plant safely or to immediate environment under accident criticality safety is dependent on a shut down the plant and maintain the conditione. Allprocess and storage limiting concentration of fissile material plant in a safe condition. There shall be systems shall be designed to be shall be designed so that either (1) an alternate system designed to allow maintained subcritical and to ensure mechanisms that could cause critical the plant to be put into a safe condition that no nuclear criticality accident can concentrations of fissile matenals are if any one control room or control area occur unless at least two unlikely, not present or (2) concentration is ss is removed from service.

independent, and concurrent or controlled by positive instrumental sequential changes have occurred in the means.

q)

Process Systems as Primary conditions essential to nuclear criticality (c) Process and storage systems shall Confinement Barners

safety, be designed to ensure that the transfer saue matedal from safe nslems to Process components and systems are hiethods of Control the primary confinement barrier.The unsafe systems is not possble as a n

design of each process system shall (a) Favorable geometry,in which consequence of any single failure or provide capability for the system to equiprnent or systems.are subcritical by operating errer.

maintain its integrity and operability as virtue of neutron leakage under worst (d) Confinement system component s necessary to protect the public health credible conditions,is the preferred shall be designed to ensure that leakage and safety. Provisions shall be included method of nuclear criticality control from equipment or from one for the safe handling of anticipated (b) Where the favorable geometry confinement zone to another nonroutine process conditions.

method of nuclear criticality controlls confinement zone cannot result in a not practical, the use of permanently condition that would result in nuclear Utility, Senices f xed neutron-absorbing materials enticahty.

Onsite utility senice systems shall be (poisons)is the next preferred method of (e)The spacin6 etween discrete b

provided when such onsite service is control.

accumulations of fissile materials shall necessary for emergency use to protect (c) Where both the favorable be controlled so as to maintain a the health and safety of the public.

geometry and the pennanently fixed subcritical state.

Onsite utility services shall meet the neutron-absorbing materials (poisons)

(f) A craicality monitoring system methods of nuclear criticality control are shall be maintained in each area where following criteriabf each utility senicenot practical, administrative controls of special nuclear material is handled, (a) The design system requtred for emergency moderation, fissile material used, or stored which will energize conditions shall provide for the meeting concentration. total fissile material, or clearfy audible slarm signals if of safety demands under normal and the use of soluble neutron absorbing accidental criticality occurs.

abnormal conditions. 'Ite design of materials (poisons) chall be employed utility senices and distnbution systems when combined with margins of safety RadiologicalProtection having safety significance shallinclude measurements or appropriate analysis Exposure Control alternate systems to the extent and engineered safety features Radiation protection systems must be necessary to maintain, with adequate Wutron Abso6es capacity, the ability to pttform safety provided for all areas and operations functions assuming a single failure.

Where solid neutron absorbing where onsite personnel may be exposed (b) Emergency utility services shall be materials (poisons) are used for the to radiation or airborne radioactive designed to permit testing of their prevention of nuclear criticality, the materials. Structures, systems. and f anctional operability and capacity, design shall provide for positive means components for which operation, including the full operational sequence to verify their continued efficacy.

maintenance and requiredinspections of each system for transfer between Soluble neutron absorbing materials may involve occupational exposure normal and emergency supply nources, may be used as a primary nuclear must be designed. fabricated. located, and the operation of associated safety criticality control provided (a) two shielded, controlled. and tested so as to systems.

Independent methods are provided to control external and internal radiation (I

(c) Provisions shall be made so that, in ensure the presenc, of the required exposures to personnel.The design must 1I the event of a loss of the primary concentration of neutron absorber and include means to:

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j 1332 Federal Register / Vol. 53, No. 78 / Friday, April 22. 1988 / Proposed Rules

=-

(a) Prevent the accumulation of information guidance set forth in for a basis of design calculation radioactive materialla those systems Regulatory Guide 3.2.5. "Standard comparable to the twenty five tem requiring access.

Format and Content of Safety Analysis whole body value used for guidance in (b) Decontaminate those systems to Reports for Uranium Enridiment to CFR Part 1007 which access is mquired.

Facilities," and experience gained in (c) Control access to arees of potential prevm' us evaluations of other types of List of Subjects for Propowl10 CFR contamination or radiatwn; fuel cycle facilities in order to determine Part "5 (d) Measure and control the individual topies for its review and Classified information. Hazardoas contaminadon of areaa requm' 'ng access; evaluation of the safety of a uranium substances, Penalty, Radia doo (e) Minimize the time required to enrichment facility. These topics are as perform work in the vicinity of follows: seismology, geology, hydrology. requirements, Secunty measures, Sou protection, Reporting and recordieepmg radaoa ctive cximponents: for example, by meteorology, site location factors, providing suffiaent space for ease of structural analysia, mechanical material. Special nuclear matenal, Uranium.

operation and desagesng equipeient for equipment anaj ma, enticality y

esse of repair and replacement: and prevention, fire / explosion prevention The authority citation for this (f) hM personnel from radiation and protection, ventijation system document is:

exposure.

analysis, identincation and sharing of (Sec. tal, sa Stat sea, as amended 62 U.S.C Radiological Alarm S stems strudures, systama, and components zm sec.20t sa Saa t im se assended 62 Y

Radiological alarm systems must be important to safety, radioactive waste U.S C Sau)).

treatment, packaging, and disposal.

provided in accemMa work areas as radiadon protection, chamiemI safety.

Apn!isas.

Deted at Rodovsils, MD, ths: toch day of appropriate to warn operating personnel accidant analysis and emergency of radiation and airborne radioactive planning, decontamination and For the Nudear Reguistory Comunission.

material concentrations above a given decommissionma, managar,*at gg i

setpoint and of concentrations of organization and quality assurance, S'"'N' h'*"-

radioactive manenalin efDuents above technical specificadons, bu: nan factors,

[m Doc. B&oens Wed 448; 8 45 am]

control limits. Radiation alarm systems operator licenamg, safeguardmg special seaso cooe 7:so-oi-48 must be designed with provisions for nuclear material, and the prow f o

calibration and testing their operability, classified information. It is expected Effhsent and Direct Radiation that each of these topics willbe M M """8 addressed separately in any safety FECEFIAL HOME LOAN BANK BOARD evaluation report prepered by the staff 12 CHI Parts 522,541,542,543,544, (a) A: appropriate eilluent systems for a uranium enrichment facility, 545, 547, 544, 549, 563, 569a, 549ti, must be provided. Means for measuring the amount of radionuclides m efDuents Questioos Related to the Regulatico of 569c, and 571 during normal operations and under Urasivus Ennchment Faci 9 ties

[No. 46-2hl accident conditions must be provided In light of the previous discussion, the for these systems. A means of measuring U.c. Nuclear Regulatory Commission is Extension of Time Period for Board the flow of the diluting medium, either particularly interested in receiving Action on Certain Outstanding air or water, must also be provided.

comments concerning the following:

Proposats (b) Areas containmg radioactive

1. Are the siting criteria set forth in materials must be provided with the General Design Criteria appropriate Date: Apnl11.198&

systems for measuring the direct and complete for uranium enrichment radiation levels in and eround these facilities?

Aotiscy: Federal Home loan Bank areas.

2. Are there factors related to Board.

Effluent Control protection of the environment and the Action: Proposed rules: extension of I

public other than t'.ie chemical toxicity time period for board action.

Facilities must be desagned to provide of the reaction products of uranlum means to limit levels as low as is hxafluoride, that are not taken into suesMAny: Pursuant to its recently rea sonably achievable the release of account in the bounding conditions in adopted regulatory review procedures.

I radioactive matenals in effluents durms the General Design Criteria?

see Board Res. No.86-269. published in normal operatioca: and control the

3. Should the criteria of Appendix B the Federal Register on Thursday, April a

i release of radioactive materials under to to Cm Part 50. "Quality Assurance 21,1988 the Federal Home Loan Bank I

decident conditions.

Criteri3 for Nuclear Power Plants and Bosni("Board ) hereby gives notice that Decommissionmg Fuel R@ang Plants," be applied in it is extending the time period for Board its present form to uranium enrichment action on the following outstanding The facihty must be designed so as to facilities?

proposed regulations outlined in facilitate decommissioning. Provisions

4. What activities should be summassNTany wone:ATtoft until must be made to facilitate performed by a licensed ope *ator and October 11,1968.

decontamination of structures and what requfrements should appfy?

This extension of time will allow the equipment, and facilitate the removal of

5. Shonid the technical epecification Board to further study the issues raise) radioactive wasies and contaminated categories applicable to feel by the proposals in light of passage of materials at the time the facihty is reprocessing plants, as set fcrth in 10 the Competitive Equality Banking Act of permanently decommfsdoned.

CFR 50.36, be applied to uractum 1987. The Board is not soliciting Review Plan Topics for NRC Staff enrichment facilities?

additional comments on these

6. Considerms the discuss}cn in this proposals. It is only extending the time The Comrnission has taken into notice concerning the health effects to period for possible Board action until account the information contained in the persons by the optake of uranium, what October 11,1988, pursuant to its recently previous paragraphs in this nonce. the value of uranium mass should be used adopted regulatory review procedures.

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