ML20206C605

Request for OMB Review & Supporting Statement Re 10CFR100, Reactor Site Criteria. Estimated Respondent Burden Will Be 5,000 H

ML20206C605
Person / Time
Issue date:	04/08/1999
From:	Shelton B NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
To:
Shared Package
ML20206C602	List: ML20206C601 ML20206C605
References
OMB-3150-0093, OMB-3150-93, NUDOCS 9905030098
Download: ML20206C605 (19)

Text

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~%fissimp EdWPdPERWORK REDUCTION ACT SUBMISSION

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Please road the instructions before ing this form. For additional forms or casistance in cornpleting this form, cont:ct your age s Paperwork Clearance

r. Send two copies of this form the collection instrument to be reviewed, the Supporting tale and any additional documentation to: Office of information and Regulatory Affairs, Office of RAenagement and Docket Library, Room 10102,72617th Street NW, Washington, DC 20503.

1..W rt ency ongmatmo request 2 oms controt number U.S. Naelear Regniatory Commission y

a.

3150- 0093 b.None 3 Type of enformaton coheden (chec! cr,e) g Type of revow requested (check one)

a. New coNedsors g

a Regular

c. Delegated e b. Revision of a cunoni., a,,,oved oo.s.n a E,nerge,,cy approvai,e sted by (daiox

c. Estension of a cunently approved comoden 5 VWi the informaten conomen have a

s. ye, significant economicimpact on a "v""

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ent w substantal number of emeu entstes?

d. Ro.mstatem,or w,h.i,t,hou,t,:v"e',"re. of.a.previously approved b No oo con ap o ed

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a.Three years from approval date Requested 6' #*'*" "

f. Existmg cohocton in use without an OMS control number

b. Other (Specify):

7. Title 10 CFR Part 100, Reactor Site Criteria

8. Agency form number (s) (if appkatWe)

9. Keywords Nxclear facility safety, geologic and seicmic bazards, early site permit

10. Abstract cperating stationary power and testing reactors pursuant to the provisions of 10 CFR Parts 50 and 10 CFR Part 100 establishes approval requirements for proposed sites for the purpose of constructin NRC desi a bases for other geological hazards, such as, faulting,quacy of proposed seismic design base uses the information required by Part 100 to assess the ade seismic bazards, and the maximum credible e:rt quake for nuclear power and test reactors.

11. Affected pubic (asse aanwy men vsaa en erners snar awy man n

12. Obhgaton to respond rasene samery men vana en cows mar ewy won M

a. Indsviduals or households

d. Farms

e. Voluntary T

b. Business or o"wr for-profit

e. Federal Govemment

b. Required to obtam or retain benefits

c. Not-for pr A institutens

f. State. Local or Tribal GovemmentT c. Mandatory

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13. Annual rept stang and recordkeeping hour burden

14. Annual reportmg and recordkeeping cost burden on mousenos orones; 1

s. Total annushred capital /startup costs

s. Numtwr of respondents I

b. Total annual costs (O&M)

b. Tots'annualresponses

1. Percentage of these responses

c. Total annushred cost requested conected electroncahy 0.0

d. Current Ous inventory

c. Total annual hours requested 5,000

e. o,,,e, enc.

d. Current OMB inventory 18,000 7

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e. Differenos (13,000) t Pmgramchange

f. Explanation of difference

2. Adpuetment

1. Program change (13,000)

2. Adjustment

15. Purpose of mformaten coltection 16, Frequency of recordkeeping or reportmg (checA atimer appry)

(48 P"7 ie *P' and af omers mer app $ se *k")

s. Recordkeeping

b. Thud-party declosure

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s. Apphostion for benefits

] e. Program planning or management ]

c. Reporting

b. Program ovaluston

f. Research

1. On occasion

2. Weekly

3. Monthly

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c. General purpose statstes T

g. Regulatory or comphance

4. Quarterly

5. Semi-annuany

6. Annually

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d. Audit

7. Bennially 7

8. Other (describe) As ineeded

17. Statetcalmethode

18. Agency contact (person who can best answer guestens reparmng me Does this informeten conecten employ statetcet methods?

Name:

Robert K. Ingram f

Phone:

mee au n.es, enseunmeween.

10/95 9905030098 990408 PDR ORG EUSOMB PDR l

19.C:rtifiscti:n for P perw rk Redu ti:n Act Submisslins On behalf of this Federal agency, I certify that the collection ofinformation encor.9 passed by this request complies with 5 CFR 1320.9.

NOTE: The text of 5 CFR 1320.9, and the related provisions of 5 CFR 1320.8 (b)(3), appear at the end of the instructions. The certification is to be made with reference to ahose regulatoryprovisions as setforth in the instructions.

The following is a summary of the topics, regarding the proposed collection ofinformation, that the certification covers:

(a) It is necessary for the proper performance of agency functions; (b) It avoids unnemsary duplication; (c) It reduces burden on small entities; (d) It uses plain, coherent, and unambiguous terminology that is understandable to respondents; 1

(c) Its implementation will be consistent and compatible with current reporting and recordkeeping practices; j

(f) It indicates the retention periods for recordkeeping requirements; (g) It informs respondents of the information called for under 5 CFR 1320.8 (b)(3):

(i)

Why the ir. formation is being collected; (ii) Use ofinformation; (iii) Burden estimate; (iv) Nature of response (voluntary, tequired for a benefit, or mandatory);

(v) Nature of extent of confidentiality; and (vi) Need to display currently valid OMB control number; i

(h) It was developed by an office that has planned and allocated resources for the efficient and effective j

management and use of the information to be collected (see note in item 19 of the instructions);

(i) It uses effective and efficient statistical survey methodology; and (j) It makes appropriate use ofinformation technology.

If you are unable to certify compliance with any of these provisions, identify the item below and explain the reason in item 18 of the Supporting Statement.

l Senature of Authortree Agency Omcel Date Signature of Omced or desem ia Dets

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(IM s,enda honen.wnc cippensacBiina or the chierinsoemation ovncer I

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FINAL SUPPORTING STATEMENT 4

T FOR I

10 CFR PART 100 l

REACTOR SITE CRITERIA l

(OMB Clearance No. 3150-0093)

Revision to Clearance Extension DESCRIPTION OF THE INFORMATION COLLECTION The Nuclear Regulatory Commission's (NRC's) regulations,10 CFR Part 100, " Reactor Site Criteria," establish approval requirements for proposed sites for the purpose of constructing and operating stationary power and testing reactors pursuant to the provisions of 10 CFR Parts 50 or 52. The information collection requirements of Part 100 are contained in Section 100.23 and Appendix A and are described below. On January 10,1997, the NRC amended Parts 100 (OMB Clearance No. 3150-0093) and 50 (OMB Clearance No. 3150-0011) by adding Sections 100.23 and Appendix S to Part 50. The section and appendix apply to applicants who apply for an early site permit, design certification, or combined license pursuant to Part 52 or a construction permit or operating license pursuant to Part 50 on or after January 10,1997. If the construction permit was issued prior to January 10,1997, the operating license applicant must comply with the seismic and geologic siting and earthquake engineering criteria in Appendix A to Part 100. Appendix A to Part 100 continues to serve as the criteria for the seismic and geologic siting and earthquake engineering for plants licensed or granted their construction permit before January 10,1997.

Section 100.23, " Geologic and seismic siting criteria," (paragraphs (c) and (d)), sets forth the principle geologic and seismic considerations that guide the NRC in its evaluation of the suitability of a site and the adequacy of the design bases established in consideration of the geologic and seismic characteristics of the site. Applicants provide information such as frequency of occurrence of earthquakes, tectonic and nontactonic surface deformation, and seismically induced floods and water waves. From these seismic and geologic hazard data, applicants determine earthquake ground motion for the seismic design basis, design bases for seismically induced floods and water waves, the potential for surface deformation and other design conditions that may be affected by earthquake ground motion, such as the potential for liquefaction, and soil and rock stability.

Appendix A, " Seismic and Geologic Siting Criteria for Nuclear Power Plants"(Sections ll and IV; and Section VI(b)(1)) requires applicants to provide the geologic and seismic data necessary to determine site suitability and provide reasonable assurance that a nuclear power plant can be constructed and operated at a site without undue risk to the health and safety of the public.

Appendix A is used as an aid for evaluating significant new geologic and seismic data as to whether or not they will have an effect on the earthquake design bases for operating nuclear power plants.

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2 Although no new applications are anticipated for the next three years, this clearance is l

necessary in the event the NRC has a need to reassess some previous seismic positions. The NRC review process for a construction permit, operating license, early site permit, design certification, or combined license as it applies to Part 100 would range from one to several years. The NRC staff reviews the Safety Analysis Report for 6 to 24 months and, if necessary, generates a request for additionalinformation. The applicant usually responds within 1 to 6 months, depending on the complexity of the issues. The average time is usually about 3 months. The responses are reviewed and a draft Safety Evaluation Report is written by the NRC staff. This document summarizes conclusions and highlights any outstanding issues.

The NRC staff arranges for a meeting and site visit to resolve any open issues. When the open issues have been resolved, the staff writes the final Safety Evaluation Report which is published and used as a basis for the remainder of the NRC licensing process which consists of meeting with the Advisory Committee on Reactor Safeguards (ACRS) and hearing, as necessary, before the Atomic Safety and Licensing Board Panel. This process usually takes about 1% years.

A.

JUSTIFICATION 1.

Need for and Practical Utility of the information Collection in support of the agency's mission regarding adequate protection of the health and safety of the public from seismic events, the NRC needs the requested information to assess the adequacy of proposed seismic design bases and the design bases for other geological hazards for nuclear power plants. It is submitted to the NRC as part of the application and supporting documentation for a construction permit, operating license, early site permit, design certification, or combined license for a nuclear power ptent.

Moreover, Section 100.23 and Appendix A, supplemented by the Standard Format, regulatory guides, and the Standard Review Plan, are used by applicants as general guidance in planning investigations of nuclear power plant sites.

2.

Aoency Use of Information The NRC reviews the geological and seismological information to determine the suitability of the proposed site for a nuclear power plant and the suitability of the I

i plant design bases established on the proposed site. A construction permit, early site permit, standard design certification, combined license, or operating license cannot be issued until these data have been reviewed and approved by the NRC.

New geological and seismological information that becomes known during the operating life of the plant is also evaluated on the basis of these criteria.

3.

Reduction of Burden Throuah Information Technoloav There are no legal obstacles to reducing the burden associated with this information collection through information technology. Moreover, NRC I

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I 3

encourages its use. However, at the current time, no licensees submit the information electronically.

4.

Effort to Identify Duolication and Use Similar Information This information does not duplicate other information being provided to NRC. All pertinent geological and seismological information conceming the nuclear site and the region around the site will be used in the analysis of that site, wnether it is supplied by the applicant or not. The availability of geological or seismological data may reduce the applicant's efforts related to site investigation.

5.

Effort to Reduce Small Busigsss Burden This information collection does not affect small businesses.

6.

Conseauences to the Federal Proaram or Policy Activities if the Collection is Not Conducted or is Conducted Less Freauently Less frequent collection of information will result in serious delays in the licensing processes of nuclear power plants or potential additional risks to the health and safety of the public.

7.

Circumstances Which Justify Variation from OMB Gu.delines There is no variation from the guidelines.

8.

Consultations Outside the NRC Opportunity to comment on the 10 CFR Part 100 information collection requirements was published in the Federal Reaister on December 23,1998 (63 1

FR 71170). No comments were received.

9.

Payment or Gift to Respondents Not app!icable.

10. Confidentiality of the information Proprietary information is protected in accordance with the provisions specified in 10 CFR 2 of the NRC's regulations.

11. Justification for Sensitive Questions This regulation does not require sensitive information.

12. JEstimate of Industry Burden and Burden Hour Colt

4 No new applications are expected during the 3-year clearance period. The estimated burden and cost for the industry is based on new geological and seismological information becoming known for one operating reactor annually.

The burden for collecting this information is estimated at 5,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. Thus, the total estimated annual burden for industry is 5,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> at a cost of $620,000 (1 x 5,000 x $124).

13. Other Additional Costs No additional costs are anticipated.

14. Estimated Annual Cost to the Federal Govemment During the 3-year clearance period, there will not be any burden to the staff regarding applications. Staff review of new geological and seismological information that becomes known for one operating reactor annually may result in approximately 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> per year at an estimated cost of $6,200 (50 x $124).

This cost is fully recovered through fee assessments to NRC licensees pursuant to 10 CFR Part 170 and/or 171.

15. Reasons for Chance in Burden The estimated burden has decreased because of a reduction in the number of estimated respondents.

16. Publication for Statistical Use This information will not be published for statistical use.

I

17. Reason for Not Displavino the Exoiration Date The requirement is contained in a regulation. Amending the Code of Federal Regulations to display information that, in an annual publication, could become obsolete would be unduly burdensome and too difficult to keep current.

18. Exceptions to the Certification Statement There are no exceptions.

B.

COLLECTION OF INFORMATION EMPLOYING STATISTICAL METHODS Appendix A of 10 CFR Part 100 allows for the acquisition of statistical data and the use of statistical methods, but does not require them.

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UNITED STATES NUCLEAR REGULATORY COMMISSION RULES and REGULATIONS TITLE 10, CHAPTER 1, CODE OF FEDERAL REGULATIONS-ENERGY 100.l(d)

PART REACTOR SITE CRITERIA 100 r

Acthority: Secs. 103,104,161.182.68

$ 100.1 Purpose.

Sec.

en 100.1 Purpose.

j Stat. 936,937,946,953, as amended (42

/> (a) The purpose of this part is to 100.2 Scope.

l' S C. 2133,2134. 2201. 2232); sec. 201, as establish approval requirements for 100 3 Definitions.

E amended. 202. 88 Stat.1242. as amended.

proposed sites for stationary power and

> 100. 4 Communications.

p 1244 (42 U.S C. 5841. 5642)-

testing reactors suhject to part 50 or part 100.8 Information collection requirements:

OMB approval 52 of this chapter.

(b) There exists a substantial base of

> Subpart A-Evaluation Factors for k.nowledge regarding power reactor Stationary Power Reactor Site Applications siting. design, construction and Before January 10,1997 and for Testin9 opr ration This base reflects that the Reactors primary factors that determine public 100.10 Factors to be considered when tiealth and safety are the reactor design.

evalualmg sites construction and operation.

10011 De'ermination of exclusion area, low (c) Siting factors and criteria are population zone. and population center important in assuring that radiological distance.

doses from normal operation and

> Subpart B-Evaluation Factors for postulated accidents will be acceptably Stationary Power Reactor Site Applications S low,that naturalphenomena and on or After January 10,1997

@ potential man-made hazards will be

> 100 20 Factors to be considered when cc appropriately accounted for in the evaluatmg sites I design of the plant,that site

> 100.21 Non seistnic site criteria characteristics are such that adaquate

> 100.23 Geologic and seismic sitmg criteria security measures to protect the plant Appendix A to Part loo-Seismic and can be developed, and that physical Geologic Siting Criteria for Nuclear Power characteristics unique to the proposed Plants site that could pose a significant impediment to the development of emergency plans are identified (d) This approach incorporates the appropriate standards and criteria for approval of stationary power and testing reactor sites. The Commission intends to carry out a traditional defense-in-

<lepth approach with regard to reactor siting to ensure public safety. Siting away from densely populated centers has been and will continue to be an important factor in evaluating applications for site approval.

100 1 December 31,1996

r 1

e 100.3 100.2 PART 100 = REACTOR SITE CRITERIA r

advance lanning, and actual

$100.2 Scope.

$ 100.3 Definitions.

thin the area The siting requirements contained in As used in this part:

distr ut o,n of residegts

, thic part apply to applications for site Combinedlicense means a combined distance from the reactor to the nearest e$ approval for the purpose of constructing construction permit and operating boundary of a densely $opulated center g and operating stationary power and license with conditions for a nuclear containing more than a out 25.000

trsting reactors pursuant to the power facility issued pursuant to residents.

provisions of part 50 or part 52 of this subpart C of part 52 of this chapter.

Power reactor means a nuclear reactor chapter.

Early Site Permit means a of a type described in S 50.21(b) or Commission approval, issued pursuant

$ 50.22 of this chapter designed to i

i to subpart A of part 52 of this chapter.

produce electrical or heat energy.

for a site or sites for one or more nuclear Response spectrum is a plot of the l

power facilities, maximum responses (acceleration, Exclusion arco means that area velocity, or displacement) of idealized surrounding the reactor, in which the e single-degree of freedom oscillators as a l

reactor licensee has the authority to

@ function of the natural frequencies of j

determine all activities including c: the oscillators for a given damping l

exclusion or removal of personnel and

' value.The response spectrum is l

property from the area. This area may be

• calculated for a specified vibratory traversed by a highway, railroad, or motion input at the oscillators

• waterway provided these are not so supports.

close to the facility as to interfere with Safe Shutdown Earthquale Ground normal operations of the facility and Motion is the vibratory ground motion provided appropriate and effective for which certain structures, systems, 3 arrangements are made to control traffic and components must be designed on the highway, railroad, or waterway, pursuant to appendix S to part 50 of this n

E in case of emergency, to protect the chapter to remain functional.

• public health and safety. Residence Surface deformation is distortion of 3 within the exclusion aies shall normally geologic strata at or near the ground be prohibited. !n any es ent, residents '

surface by the processes of folding or shall be subject to ready removal in case faulting as a result of various earth of necessitv. Activities' unrelated to forces. Tectonic surface deformation is operation of the reactor mav be associated with earthquake processes.

Testing reactor means a testingfacihty permitted in an exclusion a'rca under as defined in $ 50.2 of this chapter.

appropriate limitations, provided that no significant hazards to the public health and safety will result.

Low population zone means the area immediately surrounding the exclusion area which contains residents, the total number and density of which are such that there is a reasohable probability that appropriate protective measures could be taken in their behsifin the event of a serious accident.These guides do not specify a permissible population density or total population within this zone because the situation may vary from case to case. Whether a specific' number of people can, for example,be evacuated from a specific area, or instructed to take shelter, on a timely basis will depend on many factors such as location, number and size of highways, scope and extent of

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100.4 100.10(c)

PART 100

• REACTOR SITE CRITERIA

$ 100.4 Communicetions.

Subpart A--Evaluation Factors for (l) Appendix A.

" Seismic an.

Except where otherwise specified in Stationary Power Reactor Site Geologic Siting Cnteria for Nucles this part, all correspondence, reports, Applications Sofore January 10,1997 Power Plants," describes the nature o applications, and other written and for Testing Reactors investigations required to obtain th communications submitted pursuant t geologic and seismic data necessary t-this part 100 should be addressed to the s U.S. Nuclear Regulatory Commission, determine site suitability and to provid C ATTN: Document Control Desk.

teasonable assurance that a nuclear powe E Washington, DC 20555-0001, and

{ 100.10 Factors to be considered when plant can be constructed and operated a f copies sent to the appropriate Regional

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m a proposed site without undue risk to th lii Office and Resident inspector.

Factors considered in the evaluation of @ health and safety of the public. I Communications and reports may be a describes procedures for determining th delivered in person at the Commission,a sites include those relating both to the D quantitative vibratory ground motio pr p sed reactor design and the charac

• design basis at a site due to earthquake es ngt

,oa515 Rockville teristics peculiar to the site. It is expected and describes information needed t.

Pike, Rockville, Maryland.

that reactors will reflect through their determine whether and to what extent design, construction and operation an nuclear power plant need be designed t everemelv low probability for accidents

$100.g mrmahn Wochn w thstand the effects of surface faultmi requiremente: one approvel, that could result in release of significant

> (s) The Nuclear Regulatory quantities of radioactive fission products.

(2) Meteorological conditions at th Comr 8=sion has submitted the In addition, the site location and the site and in the surrounding area should b infor.

cNiection requirements engineered features included as safeguards considered.

conten,e o this part of the Office of against the harardous consequences of an (3) Geological and hydrologica g anage{n an Bjdget 2 accident, should one occur, should insure characteristics of the proposed site ma:

Bf 5 Reduction Act (44 U.S.C. 3501 et seq.). g a I w nsk of public exposure. In particu-E The NRC may not conduct or sponsor, g lar, the Commission will take the y and a person is not required to respond ;;; following factors mto consideration in to. a collection of information unless it determining the acceptabihty of a site for displays a currently valid OMB control a power or testmg reactor:

number. OMB has approved the (a) Characteristics of reactor design information collection requirements and proposed operation including:

contained in this part under control (1) Intended use of the reactor

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including the proposed maximum power level and the nature and inventory of contained radioactive materials; V

(b) The approved information (2) The extent to which generally a collection requirements contained in accepted engmeering standards are

@ this part appear in $ 100.23 and applied to the design of the reactor; e appendix A to this part.

(3) The extent to which the reactor h

incorporates unique or unusual features I

having a significant bearing on the L

probability or consequences of accidental release of radioactive materials; (4) The safety features that are to be engineered into the facility and those barriers that must be breached as a result of an accident before a release of radio-active material to the environment can occur.

(b) Population density and use charac-teristics of the site environs, including the exclusion area, low population tone, and population center distance.

(c) Physical characteristics of the site, including seismology, meteorology, geology and hydrology.

100-2a October 31,1997 L

I' 100.10(c) 100.11(b)

PART 100 o REACTOR SITE CRITERIA

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have a bearing on the consequences of an (1) An exclusion area of such size that (3) A population center distance of at i

escape of radioactive material from the an individual located at any point on its least one and one third times the distance l

facility. Special precautions should be boundary for two hours immediately from the reactor to the outer boundary planned if a reactor is to be located at a following onset of the postulated fission of the low population zone. In applying site whers a significant quantity of radio-product release would not receive a total this guide, the boundary of the popula-l active effluent might accidentally flow radiation dose to the whole ' body in tion center shall be determined upon 8

into nearby streams or rivers or might excess of 25 rem or a total radiation consideration of postation distribution.

find ready access to underground water dose in excess of 300 rem

• to the thyroid Political boundaries are not controlling in l

tables,

$ from iodine exposure, the application of this guide. Where very l

(d) Where unfavorable physical char $

(2) A low population zone of such large cities are involved, a greater distance l

acteristics of the site exist, the proposed E size that an individual located at any may be necessary because of total site may nevertheless be found to be To point on its outer boundary who is integrated population dose consideration.

acceptable if the design of the facility exposed to the radioactive cloud resulting 8

h includes appropriate and adequate from the postulated fission product (b) For sites for multiple reactor g campensating engineering safeguards.

release (during the entire period of its facilities consideration should be given to I { 100,11 Determination of exclusion passage) would not receive a total radia, the fo!!owing:

area, low population tone, and popu.

tion dose to the whole bpdy in excess of (1) If the reactors are m, dependent to 25 rem or a total radiation dose in excess the extent that an accident in one reactor lation center distance.

would not mitiate an accident m another, of 300 rem to the thyroid from iodine (a) As an aid in evaluating a proposed the size of the exclusion area, low popula-exposure.

cfte, an applicant should assume a fission

,, tion zone and population center distance pr: duce release from the core, the C shall be fulfilled with respect to each 8

E expected demonstrable leak rate from the reactor individually, The envelopes of the containment and the meteorological y plan overlay of the areas so calculated conditions pertinent to his site to derive shall then be taken as their respective

'o an exclusion area, a low population zone boundaries.

and population center distance. For the (2) If the reactors are interconnected purpose of this analysis, which shall set to the extent that an accident in one forth the basis for the numerical values reactor could affect the safety of opera-used, the applicant should determine the tion of any other, the size of the exclu-following:

sion area, low population zone and population center distance shall be based upon the assumption that all inter-connected reactors emit their postulated fission product releases simultaneously.

This requirement may be reduced in relation to the degree of coupling between reactors, the plobability of concomitant accidents and the proba-bility that an individual v ould not be exposed to the radiation effects from simultaneous releases. The applicant would be expected to justify to the 8

'The fission product release assumed for The whole body dose of 25 rem referred to these calculations should be based upon a major above corressonds numerically to the of:ce in a accident, hypothesized for purposes of site lifetsme accidental or emergency dose for radia.

analysis or postulated from considerations of tion wor k ers which. sccording to NCRP' possible accidental events, that would result in recommendations may be disregarded in the pottntial hasards not exceeded by those from determination of their redsstion exposure status any accident considered credible. Such acci-(see NBS Handbook 69 dated June s,19s9).

6ents have generally been assumed to result in However, neither sts use 2.or that of the 300 substantial meltdown of the core with sub-rem value ror thyroid esposure as set forth in sequent release of appreciable quantities of these site criteria suides are intended to imply j

f fission products.

that these numbers constitute acceptable limits for emergenci doses to the public under acci-dent conditions. Rather, this 25 rem whole l

body value and the 300 rem thyroid value have l

been set forth in these guides as reference l

values, which can be used in the evaluation of j

reactor sites with respect to potential reactor accidents of exceedingly low probability of l

j occurrence, and low risk of public esposure to j

t

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radiation.

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December 31,1996 100-2b i

100,11(b) 100.21(!

PART 100 e REACTOR SITE CRITERIA

~

satisfaction of the Commission the basis Subpart B-Evaluation Factors for adsorption and retention coefficients.

for such a reduction in the source term.

Stationary Power Reactor Site ground water velocity, and distances tt (3) The applicant is expected to show Applications on or After January to, the nearest surface body of water) must that the simultaneous operation of iggy be obtained from on-site measurement:

The maximum probable flood along multiple reactors at a site will not result i 100.20 Factors to be considered when with the poteatial for seismically in total radioactive effluent releases evaluating shes.

induced floods discussuiin $ 100.23 beyond the allowable limits of applicable The Commission will take the (d)(3) must be estimated using historica regulations.

following factors into consideration in data.

Note: For farther guidance in determining the acceptability of a site developing the exclusion area' the low for a stationary power reactor:

$ 100.21 Non seismic siting criteria.

(a) Population density and use Applications for site approval for population sone, and tra population characteristics of the site environs, commercial power reactors shall center distance, refcrence is made to including the exclusion area, the demonstrate that the proposed site TechnicalInformation Document 14844, population distribution, and -ite related meets the following criteria:

dated March 23, 1962, which contains a characteristics must be evaluated to (a) Every site must have an exclusior E procedural method and a sample calcula.

determine whether individual as well as area and a low population zone. as

$ tion that result in distances roughly societal risk of potential plant accidents defined in $ 100.3:

j g reflecting current siting practices of the is low, and that physical characteristics (b) The population center distance, a e

unique to the proposed site that could defined in $ 100.3, must be at least one i

, Commission. The calculations desen, bed ; pose a significantimpediment to the and one third times the distante from g

in Technical Information Document g development of emergency plans are the reactor to the outer boundary of the 14844 rnay be used as a point of de* a. identified.

Iow population zone. In applying this parture for consideration of particular 6 (b) The nature and proximity of man-guide, the boundary of the population

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site requirements which may result from o related hazards (e g., airports. dams, center shall be determined upon evalu ation of the characteristics of a transportation routes. military and consideration of population chemical facilities) must be evaluated to distribution. Political boundaries are n.

pa rticular reactor, its purpose and establish site parameters for use in controllingin the application of this method of operation.

determining whether a plant design can E guide; accommodate commonly occurring 9

(c) Site atmospheric dispersion Copies of Technical Information hazards and whether the risk of other z characteristics must be evaluated and Document 14844 may be obtained frorr.

hazards as very low.

1 dispersion parameters established such the Commission's Public Document (c) Physical' characteristics of the site, that:

Room, 2120 L Street NW., Washington, including seismology, meteorology.

(1) Radiological effluent release limit geology, and hydrology.

associated with normal operation from D.C.,

or by writing the Director of (1) Section 100.23. " Geologic and the type of facility probe met for any osed to be Nuclear Reactor Regulation. U.S. Nuctear seismic siting factors." describes the located at the site can R eg ulatory Commission, Washington, criteria and nature of investigations individuallocated offsite; and i

D.C. 2055 5.

required to obtain the geologic and (2) Radiological dose consequences c seismic data necessary to determine the postulated accidents shall meet the l

suitabihty of the proposed site and the criteria set forth in S 50.34(a)(1) of this plant design bases.

chapter for the type of facility proposec (2) Meteorological characteristics of to be located at the site; the site that are necessary for safety (d) The physical characteristics of thi analysis or that may have an impact site, including meteorology. geology, upon plant design (such as maximum seismology, and hydrology must be probs ble wind speed and precipitation) evaluated and site parameters must be identified and characterized.

established such that potential threats (3) Factors important to hydrological frem such physical characteristics will radionuclide transport (such as soil.

pose no undmisk to the type of facilit sediment. and rock characteristics, proposed to be located at the site; (e) Potential hazards associated with nearby transportation routes, industrial and military facilities must be evaluate and site parameters established such that potential hazards from such routes and facilities will pose no undue risk tc the type of facility proposed to be located at the site; (f) Site characteristics must be such that adequate security plans and measures can be developed; (g) Physical charactenstics unique to l

the proposed site that could pose e significant impediment to the development of emergency plans must be identified; (h) Reactor sites should be located away from very densely populated 100-2c December 31,1996

100.21(h) 100.23(d) 5 PART 100 e REACTOR SITE CRITERIA centers. Areas oflow population density seismic effects at the proposed site. The evaluated include scil and rock are, generally, preferred. However, in size of the region to be investigated and stability, liquefaction potential, natural determining the acceptability 6 the type of data r.irtinent to the and artificial slope stability, cooling particular site located away from a very investigations must be determined water supply, and remote safety related s

densely populated center but not in an based on the nature of the region

$ structure siting. Each applicant shall 8 evaluate all sitin E causes of failure,g factors and potential area oflow density, consideration will surrounding the proposed site. Date on such as, the physical be given to safety, environmental, the vibratory ground motion, tectonic economic, or other factors, which may surface deformation, nontectonic 1;; properties of the materials underlying resultin the site being found deformation, earthquake recurrence the site, ground disruption, and the iwceptable 8 rates, fault geometry and slip rates, site effects of vibratory ground motion that i undation material, and seismically may affect the design and operation of U00.23 Geologic and solemic siting induced floods and water waves must the proposed nuclear power plant.

o m wle be obtained by reviewing pertinent This section sets forth the principal literature and carrying out field geologic and seismic considerations that investigations. However, each a plicant guide the Commission in its evaluation shallinvestigate all geologic an seismic of the suitability of a proposed site and factors Uor example, volcank acMy) adequacy of the design bases establisned that may affect the 60:3 and operation in consideration of the geologic and ithe proposed nuclear power plant seismic characteristics of the pr sed es[ctive of whet.w. such factors are site, such that, there is a reasonab e

\\

e sI g '

assurance that a nuclear power plant

'Yd) G ol g on eis can be constructed and operated at the factors. The geologic and seismic siting proposed site without undue risk to the factors considered for design must health and safety of the public.

nelude a determination of the Safe Applications to engineering design are Shutdown Earthquake Ground Motion contained in appendix 5 to part 50 of for the site, the potential for surface (a) pplYe'obility. The re9uirements in tectonic and nontectonic deformations.

the design bases for seismically induced paragraphs (c) and (d) of this section floods and water wases, and o'ther apply to applicants for an early site design conditions as stated in paragraph permit or combined license pursuant to 3 Part 52 of this chepter, or a construction @ (d)(4) of this section.(1) Determination of the Safe g

0 permit or operating license for a nuclear

Shutdown Earthquake Ground Motion.

5 E power plant pursuant to Part 50 of this i The Safe Shutdown Earthquake Ground g chapter on or after January 10.1997, ic Motion for the site is characterized by However, for either an operating license both horizontal and vertical free-field applicant or holder whose construction ground motion response spect a at the permit was issued prior to January to, free ground surface. The Safe Shutdown 1997, the seismic and geologic siting Earthquake Ground Motion for the site criteriain Appendix A to Part 100 of is determined considering the results of this chapter continues to apply.

(b) Commencement of construction-the investigations te1ulted by paragraph (c) of this section ncertamties are The investigations required in inherent in such estimates. These paragraph (cl of this section are within uncertainties must be addressed through the scope ofinvestigations permitted by an appropriate analysis, such as a 5 50.10(c)(1) of this chapter.

probabilistic seismic hazard analysis or (c) Geological, seismological, and suitable sensitivity analyses. Paragraph engineering chorocteristics. The IV(a)(1) of appendix S to part 50 of this geological, seismological, and chapter defines the minimum Safe Engineering characteristics of a site and Shutdown Earthquake Ground Motion its environ 4 must be investigated in for design, sufficient scope and detail to permit an (2) Determination of the potential for adequate evaluation of the proposed surface tectonic and nontectenic site, to provide sufficient information to deformations. Sufficient geological, support evaluations performed to arrive seismological, and geophysical data at estimates of the Safe Shutdown must be provided to clearly establish Earthquake Ground Motion, and to whether there is a potential for surface permit adequate engineering solutions deformation.

to actual or potential geologic and (3) Determination of design bases for seismically induced floods and water

'Emarnplu of these factors include. but are not waves. The size of seismically induced deny'sIeYsIIIg supe *r'iIse Nc cha ac r stics,floods and water waves that Could affect better eccess to skilled labor for construction. better a site from either locally or distantly rail and highway access. shorter transmission line generated seismic activity must be roquarements, or less environmental impact on determined.

."pfc e

. s mYibIn facUs"fr'e7ncYuded in.(4) Determination of siting factors for

~

or impact, the other criteria included Iri inis other design conditions. Siting factors for other design conditions that must be

.ection.

December 31,1996 100-2d (neat page is 100 3)

App. A(I)

App. A(Ill PART 100

• REACTOR SITE CRITERIA APPENDIX A.-SE!SMIC AND GEOLOGIC The in ve s t igations described in this (1) The integrit y of the reactor coo SITING CRITERIA FOR NUCLEAR appendia are within the scope ofinvestigations pressure boundary, POWER PLANTS permitted by i 50.10(c)(1) of this chapter.

(2) The capabihty to shut down the rea.

1. PURPOSE Each applicant for a construction permit and maintain it in a safe shutdown condit shall investigate all seismic and geologic factors of General Design Criterion 2 of Appendia A that m,y affect the design and operation of the (3) The capability to prevent or mitia to Part 30 of this chapter requires that nuclear proposed nuclear power plant irrespective of the consequences of accidents which cc power plant structures, systems, and com-whether such factors are esplicitly included in result an potential offsite esposures compara ponents important to safety be designed to these criteria. Additional investigations and/or to the guideline esposures of this part, withstand the effects o? natural phenomena more conservative determinations then those (d) The " Operating Basis Earthquake

• such as earthquakes. tornadoes, hurricanes.

included in these criteria may be required for that earthquake which, considering the regic floods, tsunami, and seiches without loss of sites located in areas having complex geology or and local geology arid seismology and spet capabihty to perform their safety functions. It in areas of high seismicity. If an applicant characteristics of local subsurface mate is the purpose of these criteria to set forth the believes that the particular seismology and could reasonably be espected to affect principal seismic and geolctic considerations geology of a site indicate that some of these plant site during the operstmg life of the pl which guide the Commission in its evaluation of criteria, or portions thereof, need not be it is that earthquake which produces the suitability of proposed sites for nuclear satisfied, the specific sections of these er vibratory ground mo tion for w hich th power plants and the suitability of the plant should be identified in the license applica features of the nuclear power plant necess design bases established in consideration of the and supporting data to justify clearly a :

,)r continued oeeration without undue risl k seismic

.haractersstics of the g epartures should be presented.

ie health and safety of the public are desis and geolcgic d

5 proposed sites, n,

These criteria do not address investigatioi,

remain functional.

II These criteria are based on the limited E of volcanic phenomena required for site, 3 (e) A " fault" is a tectonic structure al geophysical and geological information availa- { located in areas of volcanic activity, Investiga. { which differential slippage of the adjaccet er ble to date concernmg faults and earthquake g lions of the volcanic aspects of such sites will g materials has occurred parallel to the fract occurrence and effect. They will be rettsed as be determined on a case by case basis.

plane. It is distinct from other types of gros necessar y wtsn more complete in for ma tion disruptions such as landslides, fissures, becomes assilable.

Ill. DEFINITIONS craters. A fault may base gouge or brei

11. SCOPE As used in these criteria:

between its two walls and includes any ass.

(a) The " magnitude" of an earthquake is a sted monoc!malflemure or other similar geoir These criteria, whnh apply to nuclear powcr struct ural feature.

measure of the sist of an earthquake and is plants, describe the nature of the investigations related to the energy released in the for'n of (f) " Surface faulting" is differential gros requared to obtain the geologic and seismic data seismic waves, " Magnitude" means the numeri.

displacement at or nest the surface cau necessary to determine site suitability and cal salue on a Richter seste.

directly by fault movement and is distinct fr provide reasonable assurance that a nuclear (b) The "mtensit)" of an earthquake is a nuntectonic types of ground disruptions. s.

power plant can be constructed and operated at measure of its effects on man, on man built as landshdes, fissures, and craters, a proposed site without undue risk to the (3) A " capable fault" is a fault which structures, and on the earth's surface at a health and safety of the public. They describe par ticular location. " Intensity" means the exhibited one or more of the following chas proceJures for determining the q uan tit ative numerical value on the Modified Mercalli scale.

teristics:

vibratory grounJ motion design basis at a site (c) The " Safe Shutdown Earthquake"' is (1) Movement at or near the ground surf due to earthquakes and describe mformation that earthquske which is based upon an evalus, at least onca.within the past 33,000 years needed to determine whether and to what movement of a recurring asture within the g i

tion of the maximum earthquake potential eatent a nuclear power,n! ant need tse designed 500,000 years.

considering the regional and local geology and to withstand the effects Of surface faulting.

seismology and specific characteristics of local (2) Macro seismicity in s t r u m e n t; Other geologic and seismic factors required to subsurface material. It is that earthquake which determined with records of sufficient precis be taken mio account in the sating and design produces the maximum vibrat ory groun d to demonstrate a direct relationship with of nuclear power plants are adentiheJ.

fauR motion for which certain structures, systems, and components are designed to remain func-tional. These structures, systems, and com-ponents are those necessary to assure:

)

i 8 The " Safe Shutdown Earthquake" defines that earthquake which has commonly been referred to as the " Design Basis Earthquake."

.na o rh.-- s. ** anaee.-- n

App. A(III)

App. A(IV)

PART 100 o REACTOR SITE CRITERIA (3) A structural relationship to a capable (a) Required Investiganon for Vibrefory tectonic provinces any part of which is located fault according to characteristica (1) or (2) of Ground Morfon. The purpose of the investigs-within 200 miles of the sate; this paragraph such that move ment on one tions required by this paragraph is to o')tain (7) For faults, any part of which is within could be reasonably e spected to be ac.

tnformation needed to describe the vibratory 200 miles of the site and which may be of s

companied by movement on the other, ground motion produced by the Safe Shutdown significance in establishing the Safe Shutdown in some cases, the geologic evidence of past Earthquake. All of the steps in paragraphs Earthquake, determination of whether these activity at or near the ground surface along a (a)($) through (s)(8) of this section need not be fautta are to be considered as capable faults a.e particular fault may be obscured at a particular carried out if the Safe Shutdown Earthquake This determination is required in order to site. This might occur, for enample, et a site can be clearly established by investigations and permit appropriate consideration of the geo-having a deep overburden. For these cases, determinations of a lesser scope. The investiga-logic history of such faults in estabhahang the evidence may esist elsewhere along the fault tions required by this paragrapL ruvMe an Safe Shutdown Earthquake. For guidance in from which an evaluation of its characteristics adequate basis for selection of an Operstmi fetemening which faults may be of significance in the vicmity of the site can be reasonably Basis Earthquake. The investigations shall in determains the Safe Shutdown Earthquake, based. Such evidence shall be used in determin.

include the following:

Table I of this appendia presents the minimum ing whether the fault is a capable fault withm (1) Determ6 nation of the lithologic, stral-length of f ault to be considered versus distance this definition.

igraphic, hydrologic, and structural geologic from site. Capable faults of lesser length than Notwithstanding the foregoms paragraphs conditions of the site and the region sur-those indicated in Table I and faults which are

!!!(3)(3), (2) and (3), structural association of a roundmg the site,irtcluding its geologic historyl not capable faults need not be considered in fault with geologic structural features which are (2) Identification and evaluation of tectonic determining the Safe Shutdown Earthquake, geologically old (at least pre-Quaternary) auch structures underlying the site and the region encept where unusual corrumstatices indicate as many of those found in the Eastern region of surroundmg the site, whether buried of such consideration is approprtste; the United States shall, in the absence of empressed at the surface. The evaluation should conflicting evidence, demonstrate that the fault consider the possible effects caused by man's Table I is not a capable fault within this definition.

activities such as withdrawal of fluid from or gn %,,

(h) A " tectonic provmce" is a region of the addition of fluid to the subsurface, estraction D stance from the site (miles);

length 8 North American continent characterised by a of mmerals, of the loadmg effects of dams o' 0 to 20.

I relative consistency of the geologic structurst reservoirs.

O Greater than 20 to 60 5

features contained therein.

(3) rvalustson of physical evidence 2 Greater than 50 to 100 to (i) A tectonic structure" is a large scale concerning the behavior during prior earth =

Greater than 100 to ISO 20 dsslocation or distortion within the earth's quakes of the surfacial geolvgic materials and5 Greater than l50 to 200 40 crust. Its entent is measured m miles-the substrata underlying the site from the,,

(J) A r o ne req uirin g detailed faulting lithologic, stratigraphic and structural geologic "

8Minamum length of fault ( miles) w hich investigation" is a zone withm which a nuclear studies; shall be considered in establishms Safe Shut-power reactor may not be located unless a (4) De t ermina tion of the static and down Earthquake.

detailed investigshon of the regionr1 and local dynamic engineering properties of the materials

, geologic and seismic characteristics of the site, underlying the site included thould ve proper-(8) f or capable faulta, any part of which is Z demonstrates that the need to design for; ties needed to determme the behavior of the within 200 miles' of the site and which may be

surface faulting has been properly determmed.;ll undertymg material during earthquakes and the of significance in establishms the Safe Shut-g (k) The " control width" of a fault is ther shafecteristics of the underlying material en down i' arthquake. determination of

" manimum width of the rfne contaming' transmittmg earthquake-induced motions to the (i) The length of the f ault.

I mapped fault traces, including all faulta which% foundations of the plant, such as seismic wave (ii) The relationship of the fault to regional can be reasonably inferred to have esperienced velocities, density, water content, porosity, and tectonic atructures; and differential move ment d urms Quaternary strength; (i.i) The nature, amount, and geologic times sad which Join or can reasonably be (5) Listmg of all historically reported earth-history of displacements along the fault, inferred to join the main fault trace, measured quakes w hich have affected or which could includsng particularly the estimated amount of within 10 miles along the fault's trend in both reason ably be enpected to have affected the the maximum Quaternary displacement related directiona from the potnt of nearest approach site, including the date of occurrence and the to any one earthquake along the fault.

to the site. (See hgure I of this appendis.)

f ollo win g measured or estimated data:

(b) Required In vesrtprion for Surface (1) A " response spectrum" is a plot of the magnitude or highest intenuty, and a plot of Feultms. The purpose of the msestigations manimum responses (acceleration, velocity or the epicenter or location of highest intenasty.

required by this paragraph is to obtam informa-displacement) of a f amily of idealized smgle-Where historically reported earthquakes could tion to determine whether and to what entent destve of-freedom damped oscillators agamst have caissed a maximum ground acceleration of the nuclear power plant need be designed for natural frequencies (or periods) of the oscil.

at least one-tenth the acceleration of gravity surface faulting. If the design basis for 6urface lators to e specified vibratory motion input at (0.13) at the foundations cif the proposed faulting can be clearly established t'y investi-their supports.

nuclear power plant structures, the acceleration sations of a lesser scope, not all of the steps in r intensity and duration of ground shakmg at paragraphs (b)(d) through (h)(7) of this section IV. REQUIRED INVESTIGATIONS these foundstions shall also be estimated. Smce need be carried out. The investigations shall The geologic, seismic and engineereg char.

earthquakes have been reported in terms of include the following:

acteristics of a site and its environs shall be sarious parameters such as magnitude, miensity 81f the Safe Shutdown Earthquake can be investigated in sufficient scope and detail to at a given location, and effect on ground, associated with a fault closer than 200 males to provide reasonable assurance that they are structures, and people at a specific location, the site, the procedures of paragraphs (a)(7) sufficiently well understood to per mit an some of these data may have to be estimated by and (a)(g) of this section heed not be carried adequate esclustion of the proposed site, and use of appropriate emptrical relationships. The out for successively more remote faults.

to provide sufficient information to support the comparative characteristics of the material

'In the absence of absolute dating, evidence determinations required by these criteria and to underlying the epscentral location or region of of recency of movement may be obtstned by permit adequate engmeeting solutions to actual highest intensity and of ths meterial underlying applying relative dating technique to ruptured, or potential geologic and seismic effects at the the site in transmittm3 earthquake vibratory

• • 'P'd O'

"'h****

88'""'"II#

• II'ed surfare or near surface materials or proposed site. The size of the region to be motion shalf be considered; disturb investigated and the two of data pertinent to (6) Correlation of epicenters or locations of geomorphic features.

the investigations shall be determined by the highest intensity of historically reported earth.

'The appikant shall evaluate whether or not nature of the region surrounding the proposed quakas, where possible, with tectonic structures a fault is a capable f ault with respect to the site. The investigations shall be carried out by a any part of which is located within 200 miles of characteristics outlined in paragraphs til(g Hl),

review of the pertinent literature and field the site. Epicenters or locations of highest

( 2 ),

and (3) by conducting a reasonat>le swestigations and shall snclude the steps intensity which cannot be reasonably correlated in nstigation using suitaMe geologic and outlineJ in paragraphs (a) through (c) of this with tectonic structures shall be identified with geoph ysical techniques.

se ction.

Septembef 29,1995 100 4

App MIV)

App.A(V)

PART 100 e REACTOR SITE CRITERIA (1) Determination of the lithologic, atrati.

associated with historic Isune.nl in the same shall be determined. In addition, for capable grePhic, hydrologic, and structural geologic coastal region as the site shall also be included; faults, the information required by parsgraph conditions of the site and the area surrounding (11) Local features of coastal topography (s)(3) of Section IV shall slao be taken into the site, including its geologic history; which might tend to modify Isunaml runup of account in determining the earthquakes of (2) Evaluation of tectonic structures drawdown. Appropriate available evidence greatest magnitude related to the faults. The un derlying the site, whether buried or re g arding historic local modifications in magnitude or intensity of earthquaket based on empressed et the surface, with regard to their tsunami runup or drawdown at coastal loce.

geolog6c evidence may be larger than that of the potential for caus6ng surface displacement at or tions having topography similar to that of the manimum earthquakes heatorically recorded, near the site. The evaluation shall consider the site shall also be obtained; and The accelerations at the site shall be determined possible effects caused by man's activities such (ill) Appropriate geologic and meismic assuming that the epicenters of the earthquakes as withdrawol of fluid from or addition of fluid evidence to prov6de information for establishing of greatest magnitude or the locations of to the subsurface. extraction of minerals, or the the design basis for seismically induced floods highest intensity related to the tectonic struc-loadir.g effects of dams or reservoitsi or water waves from a local offshore earth, tures are situated at the point on the structures (3) Determination of geolog6c evidence of quake, from local offanore effects of sa closest to the site; fault offset at or near the ground surface at or onshore earthquake, or from coastal sub.

(ii) Where epicenters or locations of highest near the site; sidence. This evidence shall be determined, to intensity of historically reported earthquakes (e) For faulta greater than 1000 feet long, the estent practical, by a procedure similar to cannot be ressor. ably related to tectonic struc.

any part of which is withan 9 miles' of the sate, that required in paragraphs (a) and (b) of this tures but are identified pursuant to the require.

determination of whether these faults are to be section. The probable shp characteristics of ments of paragraph (s)(6) of Section IV with considered as capable faulta.'d oifshore faults shall also be considered as well tectonic provinces in which the site is located.

(5) Listing of all historicsuy reported earth, as ?he potential for offshore slides in submarine the accelerations at the site shall be determined quakes which can reasonably be associated with material.

assuming that these earthquakes occiar at the capable faults greater than 1000 feet long, any (2) For sites located near lakes and rivers.O site.

part of which is within 3 miles' of the site, investitstions similar to those equired in para 2 (iii) Where epicenters or locations of the g including the date of occurrence and the graph (s)(1) of this section shall be carried out " highest intensity of historically reported earth-g following measured or estimated data-as sopropriate, to determ6ne the potential fora quakes cannot be reasonably related to tectonic m magnatude or highest miensity and a plot of the nuclear power plant to be esposed to o structures but are identified pursuant to the

[ the epicenter or region of highest intensity; seismically induced floods and water waves as, requirements of paragraph (a)(6) of Section IV (6) Correlation of epicenters or locations of for eaample, from the failure durms an earth.

with tectonic provinces in which the site 6s not

" highest antensity of historically reported earth.

quake of an upstream dam or from slidea of located, the acceleratsens at the site shall be quakes with capable fauffs greater than 1000 earth or debris into s pearby take, determined assuming that the epicenters or feet long, any part of which as located wethin 5 cations f highest intensity of these earth.

Y. SElSHIC AND GEOLOGIC miles of the satt:

quakes are at the closest point to the ute on the DESIGN BASES (1) For capable faults greater than 1000 boundary of the rectonse province; feet long, any part of which is within g miless (a) Derarmrnaron of Desase Basis for (iv) The earthquake producing the of the sate, determination of g l rbresory Ground Aforson. The design of each masimum vibratory acceleration at tiie site, at (i) The length of the fault.

g nuclear power plant hsil take mto account the determaned from paragraph (aHIH6) through (is) The relationship of the fault to regnnal* potennal effects of vibratory ground motion (iii) of this section shall be designated the Safe tectonic structures:

[ caused by earthquakes. The design bassa for the Shuidown Earthquake for vibratory ground (iii) T he nature, amount, and geologic. maatmum sibrator) ground motion and the motion, except as noted in paragraph (aHlHv) history of displacemen ts along the fault."' espected ubratory ground motson should be of this section. The characteristics of the Safe mcluding particularly the estimated amount of determined through evaluation of the bhutdown Larthquake shall be derived from the masimum Quaternary displacement related arismology, geology, and the seismic and geo-more than one earthquake determined from to any one earthquake along the fault; and logic history of the site and the surrounding paragraph (a)(1)(l) through (lai) of this section.

(iv) The outer limits of the fault established region. The most severe earthquakes associated where necessary to assure that the maximum by mappsng Quaternary fault traces for 10 with tectonic structures or tectonic provinces in vibratory acceleration at the site throughout miles along its trend in both directions from the the l e gion surrou nding the sate should be the frequency range of interest is included, in point of sts nearest approach to the site.

id e n t ifie d.

considering those historically the case where a causative fault is near the site.

(c) Reassered Investigerson for Scainracally reported earthquakes that can be associate d the effect of prosimity of an earthquake on the bidw ed Floods and le erer it'eres. (1) For with these structures or provmces and other spectral characteristics of the Safe Shutdown coastal sates, the investigations shallinclude the relevant factors. If f aults in the region sur-Earthquake shall be taken into account.

determination of.

roundmg the site are capat'le f aults, the most [

(i) Information regarding distantly and severe earthquakes associated with these faults T he locally generated waves of tsunami which hase should be determined by also considering their procedures in paragraphs (a)(1)(1) through affected or could have affected the site. Availa-geologic history. The vihrstory ground motion (a)(1)(iii) of this section shall be applied m a ble evidence regardmg tne runup and drawdown at at site should be then determmed by conservative manner. The determ mations assuming that the epicenters or locations cJ carried out in accordance wit h paragraphs

(

( 1)(iii) shall assure that the safe tectonic structures or E (s) 1)(li) and a)(

highest intensity of the earthquakes are situated shutdown earthquake intensity is, as a mini-at the poin t on the 8 1f the design basis for surface faulims can tectoruc provinces nearest to the site. The [ mum, equal to the manimum historic earth-be determined from a fauH closer than 5 miles earthquake which could cause the maaimumu quake intensity emperienced within the tectonic to the site, the procedures of paragraphs (b)(4) vibratory ground motion at the site should be

• Provmce in which the alte is located. In the through (b)(7) of this section need not be designated the Safe Shutdown Earthquake. The event that geological and seismological data carried out for successively more remote faults-specific procedures for determining the design warrant, the Safe Shutdown Earthquake shall

'In the absence of absolute dating, evidence basis for vibratory ground motion are given in be larger than that derived by use of the of recency of mosement may be obtained bF the fo.tlowing paragrephs.

procedures set forth m Section IV and V of the applying retarste datmg techniques to ruptured.

(1) Dererminerton of Sefe Shurdown Earth.

Appendia.

of feet, warped or otherw ise structurally gueA#, The Safe Shutdown Earthquake shall be disturbed surface of near surface materials or identified through evalusuon of seismic and l~

The maximum vibratory accelers-geomorphsc features-geologic information developed pursuant to thof tions of the Safe $hutdown Earthquake at each

'The appl 6 cant shall evaluate whether or not requirements of paragrsph IV(s), as follows; 2 of the various foundation locations of the a fault is a capable fault with respect to the magnitude or intensity which have been cors[ shall be determined taking into account th (i) The historic earthquakes of greatest nuclest power plant structures at a given site characteristics outimed in paragraphs Ill(gl(l).

(2), and (3) by conductmg a reasonable investb related with tectonic structures pursuant to the",, characteristics of the underlymg sod materialin gation usms suitable geologic and geophysical requtrementa of paragraph (a)(6) of Section IV transmitting the earthquake-ir.duced motions, te c hniq ues.

1005 September 29,1995 t

PART 100 o REACTCR SITE CRITERIA obtained pursuant to paragraphs (s)(3),(3), and TABLE 2 in evaluating the offshore effects of locai (4) of section IV. The Safe Shutdown Earth.

earthquakes shall be determined by a procedure etuminadon of Zone RequWag almuar to that used to determina the charsc.

quake shall be defined by response spectre

'I '

'"III"8 I""U880 8 corresponding to the manimum vibratory tertatics of the Safe Shutdown Earthquake in accelerations as outlined in paisgraph (a) of Width of sone paragraph V(a).

j section VI; and r e q uiring d e.

(d) Determinetton of Other Design Condh (v) Where the maximum vibratory accelers.

EsGed fsulting in, riond-(t) Son $ssbtfity. Vibratory ground tions of the Safe Shutdown Earthquake at the Magnitude of westfgs tfon f$ee motion associated with the Safe Shutdown foundations of the nuclear power plant strue.

earthquake; ffg. JJ Earthquake can cause sou instability due to tures are determired to be less than one. tenth Lessthan 5.3....

I a control width ground disruption such as flasuring. differential the acceleration of gravity (0.1 g) as a result of 3.36.4 2 a controlwidth consolidation, liquefaciton, and cratering which the steps required in paragraphs (a)(1)(1) 6.g.7.3 3 a control width is not directly related to surface faulting. The through (iv) of thss section, it shall be assumed Greater than 1.3

. 4 a control width fouowing geologic features which could affect that the maalmum vibratory accelerations of the foundations of the proposed nuclear power the Safe Shutdown Earthquake at these founds.

The largest magnitude earthquaks related to plant structures shau be evaluated, taking into tions are at least 0.18 the fault shau be used in Table 2. This account the information concerning the (2) Deremitnerton of 0perering Aast.t Earth.

earthquake shau be determined from the infor.

physical properties of materials underlying the tueke. The Operating Basis Earthquake shaU be mation developed pursuant to the requirements site developed pursuant to paragraphs (s)(l),

specified by the applicant after considerms the of paragraph (b) of Section IV for the fault.

(3), and (4) of Section IV and the effects of the seismology and geology of the region surround.

taking into account the information required Safe Shutdown Earthquake:

ing the site. If vibratory ground motion by paragraph (b)(7) of Section IV. The control (1) Areat of actual or potential surface or enceeding that of the Operating Basis Earth.

wid th u sed in Table 2 is determined by subsurface subsidence, uplift, c.

couapes quaks occurs, shutdown of the nuclest power mapping the outer limits of the fault traces resulting from plant *111 be required. Prior to resuming opers.

from information developed pursuant to pare.

(a) Natural features such as tectonic de-tions, the licensee will be required to graph (t)(7)(tv) of section IV. The control pressions and cavernous or karst terrains.

demonstrate to the Commission that no func.

width shall be used in Table 2 unless the particularly those underlain by calcareous or tional darnage has occurred to those features characteristics of the fault are obscured for e other soluble deposits; necessary for cont nued operation without significant portion of the 10 miles on either (b) Man's activities such as withdrawal of undue risk tc the health and safety of the side of the point of nearest approach to the fluid from or addition of fluid to the sub-public. The maximum vibratory ground acceler.

nuclear pow *r plant. In this event, the use m surface, estraction of mmerals, or the loading ation of the Operstmg Baus Earthquake shall Table 2 of ev width of mapped fault traces effects of dams or reservoirs; and be et least one half the maaimum vibratory more than lo miles from the pomt of neerest (c) Regional deformation, ground acceleration of the Safe Shutd own approach to the nuclear power plant may be (it) Deformational zones such as shears, Earthquake.

appropriate.

Joints, fractures, folds, or combinations of these (b) Determination of Need to Design for The zone requiring detailed faulting investi-features.

+ Jurface Feuftmp. In order to determme. sation. as determmed from Table 2, shall be c (ill) Zones of alteration or irregular E whether a nuclear power plant as required to bee used for the fault except where:

E weatherang profiles and sones of structural

% designed to withstand the effects of surface; (i) The sone req uiring detailed faulting; weakness composed of crushed or disturbed E faulting, the location of the nuclear power 8 anwestigation from Table 2 is less than one. half E materials.

l

. Plant with respect to capable faults shall be mile in width. In this case the tone shall be at)

(iv) Unrelieved residual stresses in bedrock, (v) Rocks or soils that might be unstable least one. half mile in width or a

• considered, The area over which sach of these a faults has caused surface faulting in the past is (ii) Definitive evidence concerning the because of their mineralogy. lack of consolida.

6dentified by mapptr.g its fault traces in the regional and local characteristics of the fault tion, water content, or potentially undesirsble vicinity of the atte. The fault traces are mapped Justifies use of a different value. For saample, response to esismic or other events. Seismic along the trend of the fault for 10 miles in both thrust er bedding. plane faults may requare an response characteristics to be considered shall directions from the pomt of its nearest increase m width of the tone to account for the include liquefaction, thizotropy, differential approach to the nuclear power plant because, projected dip of the fault plane; or consolidation, cratering, and fissuring, for easmple, traces may be obscured along (iii) More detailed three.dhmensional infor.

(2) Slope Ste6slity. Stability of all slopes, portions of the fault. The mesimum width of mation, such as that obtained from precise both natural and artificial, the failure of which the mapped fault traces. Called the control investigative techniques, may justify the use of could adversely affect the nuclear power plant, w idth, as then determined from this map, a narrower gone. Possible essmples of such shall be considered. An assessment shall be Buceuse surface faultmg has sometimes techniques are the use of accurate records from made of the potential effects of erosion or occurred beyond the hmet of mapped fault closely spaced drt!! holes of from closely deposition and of combinations of erosion or traces or where fault traces have not been spaced, high resolut6on offshore geophy sic al deposition with seismic setivity, taking into previously recognized, the control width of the surv e y s, account information concerning the physical fault is increased by a factor which is de-In delineating the gone requirmg detailed property of the materials underlying the site pendent upon the largest potential earthquake faulting investigation for a fault, the center of developed pursuant to paragraph (a)(1), (3),

related to the fault. This larger width delineates the tone shall coincide with the center of the and (4) of Section IV and the effects of the a rone, talled the tone requiring detailed fault at the point of nearest approach of the Safe Shutdown Earthquake, faulting investigation, in which the possibility fault to the nuclear power plant as illustrated in (3) Coolms Water Supply. Assurance of of surface faulting 6s to be determined. The Figure 1.

adequate cooling water supply for emergency following paragraphs outline the specific pro-(c) Determinerion of Dessin Asses for and lons. term shutdown decay heet removal cedures for determining the tone requiring Seismacelly Induced floods and Water Weves.

shall be considered in the design of the nuclear detailed feutting investigation for a capable The size of seismically enduced floods and power plant, taking into account information fault.

water waves which could affect a alte from concerning the physical properties of the ma-(1) Determinetton of Zone Regulesnt either locally or distantly generated seismic terials underlying the site developed pursuant Derelled Feutring In ves np rion. The zone activity shall be determined, takms into con-to raragraphs (a)(1), (3), and (4) of section IV requirms detailed faultang investigstion for a sideration the results of the investigation and the effects of the Safe Shutdown Earth-capable fault which was investigated pursuant required by paragraph (c) of section IV. Local quake and the design basis for surface faulting.

to the requirement of paragtsph (b)(1) of topographic characteristics whi;h might tend to Consideration of river blockage or diversion or Section IV shall be determined through use of modify the possible runup and drewdon at the other failures which may block the flow of the followmg table; site shall be considered. Adverse tide conditions cooling water, constal uplift or subssdence, or shall also be tsken into account in determining tsunami runup and drawdown, ans failure of the effect of the floods and waves on the site, dems and intake structures shall be included in The characteristics of the earthquake to be used the evaluation, w here appropriate.

September 29,1995 1006 1

1 1

e

App. A(V)

App. A(VI)

PART 100.o REACTOR SITE CRITERIA o

(4) Durant Structures. Those structures Safe Shutdown Earthquake and under the could result in potential offsite es posures which are not located in the immed. ate vicinity postulated concurrent condations, provided that comparable to the guideline esposures of this of the site but which are safety related shall be the necessary safety functions are maintsaned.

part. In addition to seismic loads, including deassned to withstand the effect of the Safe (2) Op e rering Asms Earthewake. The aftershocks, applicable concurrent functional Shutdown Earthquake and the design basis for Operstans Basta Earthquake shall be def6ned by and accident. induced loads shall be taken into surface faultmg determined on a comparable response spectra. AD structures, systems, and account in the design of such safety features.

basis to that of the nuclear power platit, taking components of the nuclear power plant neces.

The design provia6ons shall he based on an into account the material underlying the aary for 'contmuod operation without undue assumption that the deugn basis for surface structures and the different location with risk to the health and safety of the public shall faulting can occur in any direction and astmuth respect to that of the site.

be designed to remain functional and within and under any part of the nuclest power plant, VI. APPLICATION TO applicable stress and deformation limits when unless ev6dence indicates this assumption is not ENGINEERING DESIGN subjected to the affects of the vitiratory motion appropriate, and shall take into account the of the Operating Baals Earthquake in combme.

estimated rate as which the surface faulting (a) Wibrefory Grou :d Morton.-(t) Sa/e tion with normal operating loads. The may occur, 34urdori EarregueAr. The s abretory ground eng6neering method used to ensure that these (c) Seismscalry Induced Floods and Water motion produced oy the Safe Shutdown Earth

• attuctures, systems, and componente are Weyes and OrAer Design Condstrons. The design quake shall be def6ned by response spectra capable of withstanding the effects of the basis for seismacally induced floods and water corresponding to the maalmum vibratory Operating Bassa Earthquake shall involve the waves from either locally or distently generated accelerations at the elevations of the founds.

use of either a suitable dynamic analysts or a seismic activity and other design conditions tions of the nuclest power plant structuret suitable qualificatson test to demonstrate that determined pursuant to paragraphs (c) and (d) determine pursuant to paragraph (a)(3) of the structures, systems and components con of Section V, shall be taken into account in the Sect 6on V. The response spectra shall relate the wAstand the seismic sad other concurrent dee6gn of the nuclear power plant so as to response of the foundations of the nuclear loads, sacept where it can be demonstrated that prevent undue rask to the health and safety of power plant structures to the vibratory ground the use of an equivstent static load method the public.

mot 6on, considering such foundations to be provides adequate conservat6sm. The analysis or single degree.of. freedom damped oscillstors and test shall take into account soil-structure inter.

neglecting soil-structure interact.on effects. In actier. effects and the espected duration of f

view of the limited dets available on vibratory vibratory motiori.

I ground mot 6ons of strong earthquakes, it

.(3) Reque.

Seismic Insfewmentaffon U sup er suaisenew tsuse usua0y will be appropriate that the response Sultable instrumentation shall be prWded so" j

spectra be smoothed design spectra developed that the se.smic response of nuclear power 4

[YMEen from a series of response spectra related to the plant features in.portant to safety can be 2 3

vibratory motions caused by more than one determined promptly to permit comparison of I

earthquake.

such response with that used as the design basis.

/

"*W""up usam The nuclear power plant shall be desagned so Such a comparison as needed to decide whether

, that, af the Safe Shutdown Earth.p.ake occurs.g the plant can contmue to be operated safely

/

certam structures, systems, and components., and to permit such timely action as may be p

will remam functiocal These structures.

appropriste.

(

g systems, and components are those necessary to 8 These criterns do not addreas the need for

[ assure (1) the integrity of the reactor coolantIinstrumentation that would automatically shut l

l \\

g ges ysm;*gge o

= pressure boundary. (it) the capability to shut" down a nuclear power plant when an earth.

Mas sa* E f

j down the reactor and mamtsin it in a safe quake occurs which esceeds a predetermined condition, or (iii) the capabil&ty to ptevent or intensity. The need for such metrumentation is asnan sem or rant I

mitig ate the conseq uences of acc4 dents under considersticn.

which could result in potential offaite ex-(b) Surface Faulting (l) If the nuclear posures comparable to the guideline esposures power plant is to be located within the sone W

of this part. In addition to seismic loads.

req uiring detailed faulting in ve stiga tio n, a

including aftershocks, applicable concurrent detailed mvestigation of the regional and local functional and occident anduced loads shall be geologic and seismic charactersstics of the site FIGU R E l-DI AG R AMM ATIC IL LUST R A-taken into account in the design of these shall be carried out to determine the need to T!ON OF DELINEATION Of wlDTH OF safety related structures. systema, and com-take mio account surface faulting in the desitn 2ONE REQUIRING DET AILED F AULT-ponents. The design of the nuclear power plant of the nuclear power plant. Where 11 is ING INVESTIGATIONS FOR SPECITIC i

shall also take anto account the possit le effects determined that surface faulting need not be NUCLEAR POWER PLANT LOCATION.

of the Safe Shutdowet E ar thqua ke on the taken into accouunt, sufficient data to clearly facility foundations by ground daaruption, such Justify the determination shall be presented in as fissuring, d if f e r e ntial consolid ation.

the ticense application.

cratering, liquefact6on, and land slidin g, as (2) Where it es determined that surface required in paragraph (d) of section V, faultmg must be taken into account, the The engineering method used to ensure that applicant shall, in estabhshing the design basis the required safety functions are maintanned for surface faulting on a site take into account durms and after the vibratory ground motion evidence concernmg the regional and local associated with the Safe Shutdown Earthquake geologic and seismic characteristics of the site sh all involve the une of either a suitable and from any other relevant data.

dynamic analysis or a suitable qualification test (3) The design basis for surface faulting to demonstrate that structures, st stems and shall be taken into account in the design of the components can withstand the seismic and nuclear power plant by providsng reasonable other concurrent loods, encept where it can be sasurance that in the event of such displace-demonstrated that the use of an equivalent enent d uring faulting certain structures, static lood method provides adequate conserve-systems, and components will remain func.

tlam.

tio nal. These structures, systems, and com-The analysis or test shall take into account ponents are those necessary to esaure (1) the soil-structure interaction efforts and the antegrity of the reactor coolant pressure espected duration of vtbratory motion. It as boundary, (ii) the capabihty to shut down the permissible to design for strain limsts in escasa reactor and maintam it in a safe shutdown of yield strain 6n some of these safety relsted condition, or (iii) the capsbility to prevent or structures, systems and components during the mitigate the consequences of accidents which 100 7 September 29,1996

and the control numbers under which they are approved are as follows:

e (1) in 574.15, DOE /NRC Forrr. 741 is approved under control number 3150-0003.

(2) In 574.13, DOE /NRC Form 742 is approved under control number 3150-0004.

(3) in 574.13, DOE /NRC Form 742C is approved under control number 3150-0058.

(4) in 574.17, NRC Form 327 is approved under control number 3150-0139.

I l

l PART 75-SAFEGUARDS ON NUCLEAR MATERIAL-BMPLEMENTATION OF US/lAEA AGREEMENT 575.9 information collection requirements: OMB approval.

(b) The approved information collection requirements contained in this part appear in 5575.3, 75.7, 75.11, 75.12, 76.14, 75.21, 75.22,75.23, 75.24, 75.31, 75.32, 75.33, 75.34, 75,35, 75.36, 75.43, 75.44, and 75.45.

(c) This part contains information collection requirements in addition to those approved under the control number specified in paragraph (a) of this section. These information collection requirements and the control numbers under which they are approved are as follows:

(1) in 5 575.11 and 75.14, Form N 71 is approved under control number 3150-0056.

(2) In 5 575.31,75.32,75.33, and 75.35, DOE /NRC Form 742 is approved under control number 3150-0004.

(3) in $ 575.33 and 75.34, DOE /NRC Form 741 is approved under control number 3150-0003.

(4) In 5 575.34 and 75.35, DOE /NRC Form 740M is approved under control number 3150-0057.

(5) in 575.35, DOE /NRC Form 742C is approved under control number 3150-0058.

PART S1 STANDARD SPECIFICATIONS FOR THE GRANTING OF PATENT LICENSES 581.8 informathn collection requirements: OMB approval.

l (b) The approved information collection requirements contained in this part appear in $ 581.20, 81.32, and 81.40.

PART 95-SECURITY FACILITY APPROVAL AND SAFEGUARDING OF NATIONAL SECURITY INFORMATION AND RESTRICTED DATA 595.8 information collection requirements: OMB approval.

(b) The approved information collection requirements contained in this part appear in 5595.11, 95.15, 95.17, 95.18, 95.21, 95.25, 95.33, 95.34, 95.36, 95.37, 95.39, 95.41, 95.43, 95.45, 95.47, 95.53, and 95.57.

PART 100-REACTOR SITE CRITERIA 6

5100.8 information cols Won requirements: OMB approval.

(b) The approved information collection requirements contained in this part appear in 5100.23 and appendix A.

PART 110-EXPORT AND IMPOV OF NUCLEAR EQUIPMENT AND MATERIAL

, Pcrsonal Qualificati n Stat: mint (Licensee) - NRC 398

.====================================================================================

06/30/99 3150-0093 NRR 2

30,000 (02/22/93C - Extension) 2 10,000 (06/10/96C - Extension) 3 18,000 (01/17/97C - FR, Reactor Site Criteria incl. Seismic & Earthquake Eng. Criteria) 10 CFR 100, Appendix A, Seismic and Geologic Siting Criteria for Nuclear Power Plants

a===============================================================================

04/30/2000 3150-0101 NRR 09/30/2000 (09/29/97 error) 120 1,552 (04/18/94C - Extension) 105 28,006 (04/28/97C - Extension) 102-28,006 (09/30/97C [Dtd 7/25/97) Correction of error) 120 28,006 (10/07/97C [Dtd 9/29/97] - PR, initial License Operator Exam Rqmts) 102 28,006 (10/??/97 - OMB corrects rapns err /no cc rc'd)

RIcetor Operator and Senior Reactor Operator Licensing, Training, and Requalification Progrrems

===========================-----==================================___=_

06/30/2001 3150-0104 AEOD 1,500 75,000 (04/05/95C - Extension) 1,600 80,000 (06/15/98C - Extension)

Licensee Event Report - NRC 366, 366A, 366B

=========================.___.___._=====================================

07/31/99 3150-0107 OSP 91 1,069 (07/16/96C - Extension)

Grcnt and Cooperative Agreement Provisions

============================____========================================

03/31/2000 3150-0109 ADM/DCPM 3,288 1,486 (02/25/94C - Extension) 4,308 2,000 (03/07/97C - Extension)

Billing Instructions for NRC Cost Type Contracts

s===============================================================================

06/30/99 3150-0114 ADM/DCPM 150-300 (06/10/96C - Extension)

General Assignment - NRC 450

==========================================================u========-----

=

07/31/99 3150-0120 NMSS 4,340 39,060 (05/28/96C - Error Correction) 9,591 67,137 (07/09/96C - Extension)

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