ML20196G157
| ML20196G157 | |
| Person / Time | |
|---|---|
| Issue date: | 02/28/1995 |
| From: | NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | |
| Shared Package | |
| ML20196G123 | List: |
| References | |
| FRN-57FR47802, FRN-59FR52255, RULE-PR-100, RULE-PR-50, RULE-PR-52, TASK-*****, TASK-DG-1033, TASK-RE AD93-1-099, AD93-1-99, REGGD-01.012, REGGD-1.012, NUDOCS 9705140316 | |
| Download: ML20196G157 (41) | |
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U.S. M TEAR REGULATORY COMMISSION February 1995 OFFICE OF NUCLEAR REGULATORY RESEARCH Division 1 i
j Task DG-1033
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DRAFT REGULATORY GUIDE l
Contact:
R.M. Kenneally (301)415-6303 l
1 DRAFT REGULATORY GUIDE DG-1033 l
2 (Third Proposed Revision 2 to Regulatory Guide 1.12) 3 (Previously issued as Draft MS 140-5 and DG-1016) 4 WUCLEAR POWER PLANT INSTRUMENTATION FOR EARTHQUAKES 5
A.
INTRODUCTION s,
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6 In 10 CFR Part 20, " Standards for Protection Against Radiation," licensees are 7
required to make every reasonable effort to maintain radiation' exposures as low as is s
8 reasonably achievable. Paragraph IV(a)(4) of Proposed Appendix,S',' " Earthquake 9
Engineering Criteria for Nuclear Power Plants," to 10 CFR Part'50, " Domestic Licensing 10 of Production and Utilization Facilities," would requ'irfthat suitable instrumentation be provided so that the seismic response of nuclIakp'6wer plant features important to 11 Pararma.nbIV(a)(b)ofProposedAppendixSto10CFR Y
12 safety can t>e evaluated promptly.
13 Part 50 would reouire shutdown of the nuclear 3cwer plant if vibratory ground motion exceedingthatoftheoperatingbasjsteartbquikdgroundmotion(OBE) occurs.'
14
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15 Thisguideisbeingdevelopedtodelscribeseismicinstrumentationacceptableto 16 the NRC staff for satisfying the;re~quirements of Parts 20 and 50 and the Proposed 17 Appendix S to Part 20.
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18 Regulatory guides are issued to describe and make available to the public such 19 information as methods acceptable to the NRC staff for implementing specific parts of 20 the Commission's reiulations, techniques used by staff in evaluating specific problems 21 or postulated accidents,;and guidance 'o applicants. Regulatory guides are not x
22
,GbidanceisbeingdevelopedinDraftRegulatoryGuideDG-1034," Pre-2 s
23 Earthquake Planning and Immediate Nuclear Power Plant Operator Postearthquake 24 Actions " on criteria for plant shutdown.
e This regulatory guide is bemg issued in draft form to involve the public m the early stages of the development of a regulatory position in this ~
erse. It hee not received complete etaff review eruf does not reprewnt en official NRC etsff position.
Public commente are being acticited on the draft guide (including any implementation schedule) and its associetM regulatory onelysis or value/ impact statement. Comments should be accompanied by appropriate supporting date. Written commente may be submitted to the Rules Review and Directives Branch, DFIPS, Office of Administration, U.S. Nucieer Regulatory Commission, Washington, DC 20555. Copies of commente received may be examined at the NRC Public Document Room,2120 L Street NW., Weehington, DC. Comments will be most helpful if r.ceived by May 12, 1995.
Requeste for eingle copose of draft guides (which may be reproduced) or for placemere n en automatic distribution list for eingle copies of l
future guides in specific divisions should be made in writing to the U.S. Nucieer Reguietory Commission, Washington, DC 20555, Attention:
Office of Administration, Distribution and Mail Services Section.
i 9705140316 970422 57 47802 PDR 5'kU3 CD
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I substitutes for regulations, and compliance with regulatory guides is not 2
required.
Regulatory guides are issued in draft form for public comment to 3
involve the public in the early stages of developing the regulatory positions.
4 Draft regulatory guides have not received complete staff review and do not 5
represent official NRC staff positions.
6 Any information collection activities mentioned in this draft regulatory 7
guide are contained as requirements in the proposed amendments to 10 CFR 8
Part 50 that would provide the regulatory basis for this guide. The proposed 9
amendments have been submitted to the Office of Management and Budget for 10 clearance that may be appropriate under the Paperwork Reduction Act.
Such 11 clearance, if obtained, would also apply to any information collection t
12 activities mentioned in this guide.
13 B.
DISCUSSION 14 When an earthquake occurs, it is important to take prompt action to 15 assess the effects of the earthquake at the nuclear power plant. This 16 assessment includes both an evaluation of the seismic instrumentation data and 17 a plant walkdown.
Solid-state digital time-history accelerographs installed 18 at appropriate locatic s will provide time-history data on the seismic 19 response of the free-field, containment structure, and other Category I 20 structures.
The instrumentation should be located so that a comparison and 21 evaintion of such response may be made with the design basis and so that 22 occupational radiation exposures associated with their location, installation, 23 and maintenance are maintained as low as reasonably achievable (ALARA).
24 Free-field instrumentation data would be used to capare measured 25 response to the engineering evaluations used to determine the design input 26 motion to the structures and to determine whether the OBE has been exceeded 27 (see Draft Regulatory Guide DG-1034).
Foundation-level instrumentation would 28 provide data on the actual seismic input to the contoinment and other 29 buildings and would quantify differences between the vibratory ground motion 30 at the free-field and at the foundation level.
The instruments located at the
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31 foundation level and at elevation in the structures measure responses that are 32 the input to the equipment or piping and would be used in long-term 33 evaluations (see Draft Regulatory Guide DG-1035, " Restart of a Nuclear Power 34 Plant Shut Down by a Seismic Event").
Instrumentation is not located on 35 equipment, piping, or supports since experience has shown that data obtained 2
1 at these locations are obscured by vibratory motion associated with normal S
2 plant operation.
The guidance being developed in Draft Regulatory Guide DG-1034 is based 3
4 on the assumption that the nuclear power plant has operable seismic instrumen-5 tation, including the equipment and software needed to process the data within 6
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after an earthquake. This is necessary to determine whether plant 7
shut down is required. This determination will be made by comparing the 8
recorded data against OBE exceedance criteria and the results of the plant 9
walkdown inspections that take place within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of the event.
10 It may not be necessary for identical nu:: lear power units on a given 11 site to each be provided with seismic instrutnentation if essentially the same 12 seismic response at each of the units is expected from a given earthquake.
13 An evaluation of seismic instrumentation noted that instruments have 14 been out of service during plant shutdown and sometimes during plant 15 operation. The instrumentation system should be operable and operated at all 16 times.
If the seismic instrumentation or data processing hardware and 17 software necessary to determine whether the OBE has been exceeded is 18 inoperable, the guidelines in Appendir A to Draft Regulatory Guide DG-1034 19 would be used.
The characteristics, installation, activation, remote indication, and 20 21 maintenance of the instrumentation are described in this guide to help ensure (1) that the data provided are comparable with the data used in the design of 22 23 the nuclear power plant, (2) that exceedance of the OBE can be determined, and 24 (3) 1 hat the equipment will perform as required.
25 The appendix to this guide provides definitions to be used with this 26 guic'nce.
27 nolders of an operating license or construction permit issued prior to 28 the implementation date to be specified in the active guide may voluntarily 29 implement the methods to be described in the active guide and the methods 30 being developed in Draft Regulatory Guides DG-1034, " Pre-Earthquake Planning 31 and Immediate Nuclear Power Plant Operator Postearthquake Actions," and 32 DG-1035, " Restart of a Nuclear Power Plant Shut Down by a Seismic Event."
33 C. REGULATORY POSITION 34 The type, locations, operability, characteristics, installation, l
35 actuation, remote indication, and maintenance of seismic instrumentation l
3 l
l i
c
1 described below are acceptable to the NRC staff for satisfying the require-2 ments in 10 CFR Part 20,10 CFR 50.65(b)(2), and Paragraph IV(a)(4) of 3
Proposed Appendix S to 10 CFR Part 50 for ensuring the safety of nuclear power 4
plants.
5 1.
SEISMIC INSTRUMENTATION TYPE AND LOCATION 6
M Solid-state digital instrumentation that will enable the 7
processing of data at the plant site within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of the seismic event 8
should be used.
9 M
A triaxial time-history accelerograph should be provided at each 10 of the following locations:
11 1.
Free-field.
12 2.
Containment foundation.
13 3.
Two elevations (excluding the foundation) on a structure 14 internal to the containment.
15 4.
An independent Category I structure foundation where the 16 response is different from that of the containment 17 structure.
18 5.
An elevation (excluding the foundation) on the independent 19 Category I structures selected in 4 above.
20 6.
If seismic isolators are used, instrumentation should be 21 placed on both the rigid and isolated portions of the same 22 or an adjacent structure, as appropriate, at approximately 23 the same elevations.
24 M
The specific locations for instrumentation should be determined by 25 the nuclear plant designer to obtain the most pertinent information consistent 26 with maintaining occupational radiation exposures ALARA for the location, 27 installation, and maintenance of seismic instrumentation.
In general:
4
m 1
1,3,1 The free-field sensors should be located and installed so 2
that the effects that are associated with certain features, buildings, and 3
components will be absent from the recorded ground motion.
4 1.3.2 The instrumentation should be placed at locations that have 5
been modeled as mass points in the building dynamic analysis so that the 6
measured motion can be directly compared with the design spectra.
The 7
instrumentation should not be located on a secondary structural frame member 8
that is not modeled as a mass point in the building dynamic model.
9 1,3,3 A design review of the location, installation, and 10 maintenance of proposed instrumentation for maintaining exposures ALARA should 11 be performed by the facility in the planning stage in accordance with 12 Regulatory Guide 8.8, "Information Relevant to Ensuring that Occupational 13 Radiation Exposures at Nuclear Power Stations Will Be As low As Is Reasonably 14 Achievable."
15 1,3,4 Instrumentation should be placed in a location with as low a 16 dose rate as is practical, consistent with other requirements.
17 1,3,5 Instruments should be selected to require minimal 18 maintenance and in-service inspection, as well as minimal time and numbers of 19 personnel to conduct installation and maintenance.
20 2.
INSTRUMENTATION AT MULTI-UNIT SITES l
l 21 Instrumentation in addition to that installed for a single unit will not f
22 be required if essentially the same seismic response is expected at the other 23 units based on the seismic analysis used in the seismic design of the plant.
24 However, if there are separate control rooms, annunciation should be provided 25 to both control rooms as specified in Regulatory Position 7.
26 3.
SEISMIC INSTRUMENTATION OPERABILITY 27 The seismic instrumentation should operate during all modes of plant 28 operation, including periods of plant shutdown.
The maintenance and repair 5
1 procedures should provide for keeping the maximum number of instruments in 2
service during plant operation and shutdown.
3 4.
INSTRUMENTATION CHARACTERISTICS 4
M The design should include provisions for in-service testing.
The 5
instruments should be capable of periodic channel checks during normal plant 6
operation.
7 M
The instruments should have the capability for in-place functional 8
testing.
9 4.3 Instrumentation that has sensors located in inaccessible areas 10 should contain provisions for data recording in an accessible location, and 11 the instrumentation should provide an external remote alarm to indicate 12 actuation.
13 4.4 After actuation, the instrumentation should record the 3 seconds 14 of low amplitude motion prior to seismic trigger actuation, continue to record 15 the motion during the period in which the earthquake motion exceeds the 16 seismic trigger th eshold, and continue to record low amplitude motion for a 17 minimum of 5 seconis beyond the last exceedance of the seismic trigger 18 threshold.
19 4.5 The instrumentation should be capable of recording 25 minutes of 20 sensed motion.
21 4.6 The battery should be of sufficient capacity to power the 22 instrumentation and sense and record (see Regulatory Position 4.5) 25 minutes
?.3 of motion, with no battery charger, over a period of not less than the channel 24 check test interval (Regulatory Position 8.2).
l 25 4.7 Acceleration Sensors 26 4.7.1 The dynamic range should be 1000:1 zero to peak, or greater; 27 for example, 0.00lg to 1.0.
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9 6
1 4.7.2 The frequency range should be 0.20 Hz to 50 Hz or an 2
equivalent demonstrated to be adequate by computational techniques applied to 3
the resultant accelerogram.
4 M
Recorder l
5 4.8.1 The sample rate should be at least 200 samples per second in 6
each of the three directions.
l 7
4.8.2 The bandwidth should be at least from 0.20 Hz to 50 Hz.
8 4.8.3 The dynamic range should be 1000:1 or greater and be able to 9
record at least 1.0g 0 to peak.
l 10 M Seismic Trigger. The actuating level should be adjustable and 11 within the range of 0.00lg to 0.02g.
12 5.
INSTRUMENTATION INSTALLATION 13 M
The instrumentation should be designed and installed so that the 14 mounting is rigid.
15 M
The instrumentation shoulo be oriented so that the horizontal axes 16 are parallel to the orthogonal horizontal axes assumed in the seismic 17 analysis.
18 5.3 Protection against accidental impacts should be provided.
19 6.
INSTRUMENTATION ACTUATION 20 M
Both vertical and horizontal input vibratory ground motion should 21 actuate the same time-history accelerograph. One or more seismic triggers may 22 be used to accomplish this.
j 23 M
Spurious triggering should be avoided.
D 7
1 6.3 The seismic trigger mechanisms of the time-history accelerograph 2
should be set for a threshold ground acceleration of not more than 0.029 3
7.
REMOTE INDICATION 4
Activation of the free-field or any foundation-level time-history 5
accelerograph should be annunciated in the control room.
If there is more 6
than one control room at the site, annunciation should be provided to each 7
control room.
8 8.
MAINTENANCE 9
M The purpose of the maintenance program is to ensure that the 10 equipment will perform as required. As stated in Regulatory Position 3, the 11 maintenance and repair procedures should provide for keeping the maximum 12 number of instruments in service during plant operation and shutdown.
13 M
Systems are to be given channel checks every 2 weeks for the first 14 3 months of service after startup.
Failures of devices normally occur during 15 initial operation. After the initial 3-month period and 3 consecutive 16 successful checks, monthly channel checks are sufficient.
The monthly channel 17 check is to include checking the batteries. The channel functional test 18 should be performed every 6 months. Channel calibration should be performed 19 during refueling.
20 D.
JMPLEMENTATION 21 The purpose of this section is to provide guidance to applicants and 22 licensees regarding the NRC staff's plans for using this regulatory guide.
23 This proposed revision has been released to encourage public 24 participation in its development.
Except in those cases in which the 25 applicant proposes an acceptable alternative method for complying with the 26 specified portions of the Commission's regulations, the method to be described 27 in the active guide reflecting public comments will be used in the evaluation 28 of applications for construction permits, operating licenses, combined 29 licenses, or design certification submitted after the implementation date to
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30 be specified in the active guide.
This guide would not be used in the 8
1 evaluation of an application for an operating license submitted after the 2
implementation date to be specified in the active guide if the construction 3
permit was issued prior to that date.
l l
9
1 APPENDIX 2
DEFINITIONS 3
Acceleration Sensor. An instrument capable of sensing absolute acceleration 4
and transmitting the data to a recorder.
5 Accessible Instruments.
Instruments or sensors whose locations permit ready 6
access during plant operation without violation of applicable safety 7
regulations, such as Occupational Safety and Health Administration (OSHA), or 8
regulations dealing with plant security or radiation protection safety.
9 Channel Calibration (Primary Calibration). The determination and, if 10 required, adjustment of an instrument, sensor, or system such that it responds 11 within a specific range and accuracy to an acceleration, velocity, or 12 displacement input, as applicable, or responds to an acceptable physical 13 constant.
14 Channel Check. The qualitative verification of the functional status of the 15 instrument sensor.
This check is an "in-situ" test and may be the same as a 16 channel functional test.
17 Channel Functional Test (Secondary Calibration).
The determination without 18 adjustment that an instrument, sensor, or system responds to a known input of 19 such character that it will verify the instrument, sensor, or system is 20 functioning in a manner that can be calibrated.
21 Containment - See Primary Containment and Secondary Containment.
22 Nonaccessible Instruments.
Instruments or sensors in a location that does not 23 permit ready access during plant operation because of a risk of violating 24 applicable plant operating safety regulations, such as OSHA, or regulations 25 dealing with plant security or radiation protection safety.
l 26 Operatina Basis Earthouake Ground Motion (OBE). The vibratory ground motion l
27 for which those features of the nuclear power plant necessary for continued 28 operation without undue risk to the health and safety of the public will 29 remain functional. The value of the OBE is set by the applicant.
10
1 Primary Containment. The principal structure of a unit that acts as the I
2 barrier, after the fuel cladding and reactor pressure boundary, to control the 3
release of radioactive material.
The primary containment includes (1) the 4
containment structure and its access openings, penetrations, and appurte-5 nances, (2) the valves, pipes, closed systems, and other components used to 6
isolate the containment atmosphere from the environment, and (3) those systems 7
or portions of systems that, by their system functions, extend the containment 8
structure boundary (e.g., the connecting steam and feedwater piping) and 9
provide effective isolation.
10 Recorder. An instrument capable of simultaneously recording the data versus 11 time from an acceleration sensor or sensors.
12 Secondary Containment. The structure surrounding the primary containment that 13 acts as a further barrier to control the release of radioactive material.
14 Seismic Isolator. A device (for instance, laminated elastomer and steel) 15 installed between the structure and its foundation to reduce the acceleration 16 of the isolated structure, as well as the attached equipment and components.
17 Seismic Triaaer. A device that starts the time-history accelerograph.
18 Time-History Acceleroaraoh. An instrument capable of sensing and permanently 19 recording the absolute acceleration versus time.
The components of the time-20 history accelerograph (acceleration sensor, recorder, seismic trigger) may be 21 assembled in a self-contained unit or may be separately located.
22 Triaxial. Describes the function of an instrument or group of instruments in 23 three mutually orthogonal directions, one of which is vertical.
i 1
D l
11
1 MGULATORY ANALYSIS 2
A separate regulatory analysis was not prepared for this regulatory 3
guide.
The draft regulatory analysis, " Proposed Revision of 10 CFR Part 100 4
and 10 CFR Part 50," was prepared for the proposed amendments, and it provides 5
the regulatory basis for this guide and examines the costs and benefits of the 6
rule as implemented by the guide.
A copy of the draft regulatory analysis is 7
available for inspection and copying for a fee at the NRC Public Document 8
Room, 2120 L Street NW. (Lower Level), Washington, DC, as Enclosure 2 to 9
Secy 94-194.
I UNITED STATES FIRST CLASS MAIL NUCLEAR REGULATORY COMMISSION POSTAGE ANo FEES PAfD WASHINGTON, D.C. 20555-0001 USNRC PERMIT No. G 67 OFFICIAL BUSINESS PENALTY FoR PRIVATE USE, $300 e
12
AP93-1 PM szzss Proposed Rules r deai a+-
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W1.53. No.133 j
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Monday, October 17, 1994 H
This section of the FEDERAL REGISTER Attention: Docketing and Service distances and population density limits contains notices to the pJbuc of the proposed Branch.
into the regulations. On April 28,1977, C
1ssuance of mies and reOutatms. The Deliver comments to 11555 Rockville Free Environment, Inc. et al., filed a
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pgose of these notices is to giva interested Pike, Rockville, Maryland, between 7:45 petition for rulemaking (PRM-50-20).
L f
am and 4:15 pm, Federal workdays.
The remaining issue of this petition the n the nal rules.
Copies of the regulatory analysis, the requests that the central lowa nuclear j
cuvis utunental assenment and finding Project md other reactou be sited at of no significant impact, and comments least 40 miles from major population.
[, ;
NUCLEAR REGULATORY received snay be examined at the NRC centers. In August 1978, the COMMISSION Public Document Room at 2120 L Street Commission directed the NRC staff to NW. (Lower Level), Washington, DC.
develop a general policy statement on i
10 CFR Parts 50,52 and 100 nuclear power reactor siting. The FOR FURTHER INFORMATION CONTACT: Dr.
i RIN 3150-AD93 Andrew J. Murphy, Office of Nuclear Report of the Siting Policy Task Force" (W
625) was issued in August Regulatory Research, U.S. Nuclear Heactor Site Criteria including Seismic Regulatory Commission, Washington 1979 and provided recommendations and Earthquake Engineering Criteria DC 20555, telephone (301) 415-6010,
%ardmg siting of future nuclear power react rs. In the 1980 Authorization Act I r Nuclear Power Plants and concerning the seismic and earthquake q
Proposed Denial of Petiticn From Free engineering aspects and Mr. Leonard f r the EC, the Congmss hcted the q
Environment, Inc. et al.
Soffer, Office of Nuclear Regulatory NRC to decouple siting from design and i
AGENCY: Nuclear Regulatorv "esearch, U.S. Nuclear Regulatory s tin ul 2 19 5
5 350),
Commission, ummission Washington, DC 20555, the NRC issued an Advance Notice of C
ACTION: Proposed rule and proposed tekphone (301) 415-6574, concerning I'
denial of petition from Free ther siting aspects, p
" o "% MPRW regarding revision of the reactor site Environment,Inc et al SUPPLEMENTARY INFORMATION:
criteria, which discussed the 8
- I
SUMMARY
- The Ndear Regulatory I. Backgmund-Task Force and sought pubuc Commission (NRC)is proposing to II. Objectives.
comments. The pmposed rulemaking tmend its regulations to update the Ill. Genesis, crittria used in decisions regarding TV. Alternatives, was deferred by the Commission in
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power reactor siting, including geologic, V. Major Changes.
December 1981 to await development of seismic, and earth uake engineering A. Reactor Siting Criteria (Nonseismic).
a Safety Goal and improved research on considerations for ture nuclear Power B. Seismic and Eanbquake Engineering accident source terms. On August 4.
h Criteria.
1986 (51 FR 23044),the NRC issued its pl:nts. The proposed rule would allow VI. Related Regulatory Guides and Standard Poli Statement on Safety Goals that state 7 quantitative health objectives NRC to benefit from experience gained Review Plan Section.
in the application of the procedures and VU. Future Regulatory Action.
with regard to both prompt and latent methods set forth in the current VIH. Heferenced Documents' cancer fatality risks. On December 14, regulation and to incorporate the rapid tX. Electronic Format.
1988 (53 FR 50232), the NRC denied sdvancements in the earth sciences and X. Questions.
earthquake e ineering.16 addition, this XI. Finding of No Significant Environmental PRM-100-2 on the basis that it would proposed rul nefits from the public Impact: Availability.
unnecessarily restrict NRC's regulatory comments received on the Ent XII. Paperwork Reduction Act Statement.
siting policies and would not result in
(
XIll. Regulatory Analysis.
a substantial increase in the overall 4
Proposed revision of the tions.
ublic health and
!f XIV. Regulatory Flexibility Certification.
protection of the fpossible renewed 0
This proposed rule priman consists of XV.Backfit Analysis, safety. Because o two separate changes, name y, the source term and dose considerations, I. Background interest in power reactor siting, the NRC 1
ispm dbW e rukdbg b %
5 and the seismic and earthquake The present regulation mgarding area.The Commission proposes to engineering considerations of reactor Proposing to deny the remaining issue was promulgated A 12,1962 (27 TS mart of this rulemaWg acdon.
I reactor site criteria (10 CFP part 100) address the remaining issue in PRM.
siting. The Commission is als f
j 3509). NRC staff dance on exclusion A pendix A to 10 CFR part 100, in petition (PRM-50-20) filed by Free area and low population zone sizes as "Sefsmic and Geologic Siting Criteria Environment,Inc. et al.
well as population density was issued for Nuclear Power Plants," was DATES: Comment period expires in Regulatory Guide 4.7," General Site originally issued as a proposed February 14,1995. Comments received Suitability Criteria for Nuclear Power regulation on November 25,1971 (36 FR cfter this date will be considered ifit is Stations," published for comment in 22601), published as a final regulation practical to do so, but the Commission September 1974. Revision 1 to this on November 13,1973 (38 FR 31279),
is able to assure consideration only for guide was issued in November 1975.On and became effective on Demmber 13, comments received on or before this June 1,1976, the Public Interect 1973.There have been two amendments dat2.
Research Group (PIRG) filed a petition to 10 CPR part 100, appendix A.The ADDRESSES: Mail written comments to:
for rulemaking (PRM-100-2) requestin8 first amendment, issued November 27, Secretary, U.S. Nuclear Regulatory that the NRC incorporate minimum 1973 (38 FR 32575), corrected the final
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Commission Washington,DC 20555, exclusion area and low population zone regulation by adding the legend under l
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52256 Federal Regist:r / Vol. 59. No.199 / Monday, October 17, 1994 / Proposed Rules the diagram. & second amendment applying the existing regulation and design requirements rather than si.ing.
reeulted fmm a petition for rulemaHrg fmm rece.mh; (2) resolve interpretive It is desirable to state basic site criteria (PRM-100-1) requesting that an opinion questions; (3) provide needed regulatory which, through importance to risk, have
- l be issued that would interpret and flexibility to incorporate state-of-the-art been shown to be key to assuring public clarify Appendix A with respect to the improvements in tne geosciences and health and safety. Funber, mignmcant determination of the Safe Shutdown earthquake engineering; and (4) simplify advances in understanding severe Earthquake. A notice of filing of the the language to a more " plain English" accident behavior,includmg fission petition was published on May 14.1975 text. In addition, the proposed pmduct release and transport. as well as (40 FR 20983). The substance of the mgulatory action wiHbenefit from in the earth sciences and in earthquake 3
petitioner's pmposal was accepted and public comments mceimd on the first engineering have taken place sinco the 1
published as an immediately effective proposed revision of the regulations and promulgation of the present regulatioh final regulation on knuary 10,1977 (42 Suidance documents.
and deserve to be reflected in the FR 2052).
W proIwd mgulatory action would regulations.
f N first proposed revision to these apply to applicants who apply for a h second alternative considered i
regulations was published i r public construction permit, operating license.
was replacement of the existing i
comrnent on October 20.1992 (57 FR preliminary design approval. final regulation with an entirely new 47802). b availability of the five draft design approval, manufacturing license. regulation.1 his is not an ac&ptable early comb, site permit. design certification. or alternative because the provisions of the regulatory guides and the standard med license on or after the existing regulations form part of the review plan socrion that wem developed to pmvide guklaea on meeting the effodive date of the finalregulations.
Licensing bases for many of the proposed regulations was published on Criteria not associated wilh the operating nuclearpower plants and i
November 25,1992 (57 FR 55601). The selection of the site or establisbrnent of
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others that are in various stages of
,1
. comroent period for the proposed the Safe Shutdown Earthquake Ground obtaining operating limases. hmfore.
regulatims was extended two times.
Mot on (SSE) have been placed into 10 these provisions should remain in form First. tk NRC staffinitiated an CR part 50. '1111s action is consistent and effect, extens3cn (58 FR 271)imm Febmary 17, with the location ofother design The approach of establishing the 1993 ta March 24,1993. to be consistent rguimmets in 10 CN part 50.
revised requirements in new sedions to with the comment period on the draft nacause the revised crateda presented to CFR part 100 and relocating plant regulatory guides and standard review in the pmposed regulation would not be design requimments 1010 CFR part 50 plan sectim. Seced,in sesponse to a applied to existing plants, the hoensing while retaining the existing regulation request from the public.the comment
. baws for existing nuclear power plants. was chosen as the best alternative.h period was extended to June 1.1993 (58 must mmain part & mgulaums" public will benefit imm a clearer, more FR 16377).
mi m, tQ non seistnic and salsmi" uniform. and more consistent licensing h proposed regulations published mactor site cnteria for current plants pmcess that incorpwates updated j
on October 20.1992 (57 FR 47802) and w uld be retained as subpart A and information and is sub}ect to fewer draft guidance dacumente cited in the appendix A to 10 CFR part 100, interpretatious.b NRC staff will i
avallabihty nneka publi.sbd on respectively, h proposed revised benefit immimpmved tory L
Novembor 25,1992 (57 FR 55601) are reactor site criteria would be added as bphnentath(both caland f
withdrawn becaura of the substantive sub art B in to CFR part 100 and would legal), fewer interpretive debates, and t'
nature of the chstges to be made in gf[hQP increased regolstory flexibility.
s sem aw te d N
to public cernments and are reshwith tb second pror.
regulations. Non-c.camle site crueda Applicants will derive the same benefits revision of the regulations presented in w uid t>e added as a new 5100.21 to in addition to avoiding licensing delays q
- F this dac",,=
subpart B in 10 CFR part 100.&
caused by unclear regulatory criteria on selsmic and geologic siting requirements.
i ]
II. Objectives would be added as a new $100.23 to V.Majorth=ces N objectives of this proposed subpart B in 10 CFR part 100 b dose A. Reactor Siting Crfterfa [Nonsefsmic) b c si eria for futuro ngi crite would ocated in Sina p-niga*= of the reactor site i
sites that. based upon rience and 10 CFR part 50 (S50.34(a)and criteria in 1962, thenrnmw^a_ has b
importana to risk.hav n shown as Appendix S. respectively).Because approved more than 75 sites $ar nuclear k to protecting publichealth and Appendix S is not self exemeine Powerreactors and has had an applicable sections of part 50 (S 50.34 OPPortunhy to review a numberof sa
- 2. bde a stable regulatory basis for and S 50.54)are revisedto reference others. In Maa_ light-water i
seismic and geologic siting an'd appendix S.ne proposed regulation commerciapler raar+nrs have
"'"*"lat abat 1800 saador. years of applicable certhquake engineering would also maka ochforming design of future nuclear plants amendments to to CFR part 52.Section Operating wm w. in th Unlied thatwillupdate and regulatory 52.17(a)(1) would be amended to tr> fled States. As a result of these site reviews requirements and provide flexible changes in 50.34(a)(1) and to CPR Part and operational experience, a great deal structure to pertnit consideration of new 100.
of Lasight has boon gained mgarding the technicalunderetandings; and IV* Ahemati'*'
E"*
P ants as wellas the site factors t l
- 3. Relocate sourm tenn and dose l
requirements that apply primarily to The Grst alternative considered by the influena risk. In addition, an extensive.
plant design into 10 Cm part 50.
Commieston was to continue using research e!Iort has been conducted to current regulations for site suitability understand accident phenomena.
III. Genesis detenninations. his is not considered including fission product release and
& proposed regulatory action an acceptable alternative. Accident.
transport. This extensive operational reDeds changes that are Intended to (1) source tertns and dose calculations experience together with the insights l
benefit from the experience gained in currently primarily influence plant gained from recent severe accide l
4 e
)
Fed:ral Register / Vol. 59, No.199 / Monday, October 17, 1994 / Proposed Rules 52257
.1 research as well as numerous risk accident source terms, currently under comments, the Commission is g
studies on radioactive material releases development within the NRC staff as proposing,in the present rule, to retain to the enviroaurent under wvere well as in the industry'.
the use of somoe term and dow accident conditions have all conDrmed The pro relocation of sourw calculations,in part 50, to verify that an that present commercial power reactor term and calculations to part 50 applicant's proposed exclusion area k
design, construction, operation and represent a partial decoupling of siting distance is adequate to assum that the b
siting is expected to effectively limit from amident source term and dose radiological does to an individual will 7
risk to the public to very low levels.
calculations. The siting criteria are be acceptably lowin the event of a i,
mee risk studies include the early envisioned to be utilized together with postulated accident. However, as noted E
- Reactor Safety Study" (WASH-1400),
standardized plant designs whose above,if source term and dose I
published in 1975, many Probabilistic features will be cert 1Dod in a separate calculations are used in coQunction b
Risk Assessment (PRA) studies design certification rulemakin8 with standardized designs, unlimited conducted on individual plants as well pmcedure. Each of the standardized plant tradeoffs to compensate for poor as several specialized studies, and the designs would specify an 6tmo.pheric site conditions w9uld not be permitted.
rec:nt " Severe Accident Rasks: An dilution factor that would be required to For plants that do not involve r.
Assessment for Five U.S. Nuclear Power be met, in order to meet the dose criteria standardized designs, the source term H
Plants," (NUREC-1150), issued in 1990, at the exclusion area boundary, For a and dose calculations would continue to Advarxed readordesigns currently given standardized design, a site having provide assurance that the site is-under review are expected to result in relatively poordispersion acceptable for the proposed design.
svan lower risk and im ved safety characteristics would uire a larger The present regulation requires that compared toexisting p ts. Hence, the exclusion anos distan=
one having the exclusion aree be of such size that substantial base of knowledge regarding good dispersion chamderistics.
power reactor sitag, desy,n, Additionaldesign features would be an individual located at any Point on its construction and operation reflects that discouraged in a standardized design to g '""postula comptions.asase for otherwise poor site I' '
lon th factors that determine pmdud M-ouh mb pub ic th and safety are the reactor ma total radiation dose in excess of 25 rem 3
design, construction and tion Although individual plant tradeoffs Siting factors and critekaTowev.
would be discouraged for a given to the whole body or 300 rpm to the q[.
er, rse important in assuring that standardized design, a different thyroid gland. A footnotein the nt rtdirlogical doses from normal standardized design could require a regulation notes that a whole y dose a
eperation and postulated saidents will different =*=a=pharic dilution lador.
of 25 4em has been =tasad to correspond
- 2 be acceptably low,that natural Foren=sa= plants that do not involve a nuinerically to the once in a lifetime accidental or -
d 7 oes to henomena and potential man.made standardiaod design, the source term radiation wakers Ehim could be azards will be appropriately accounted and dose ariteria willcontinue to for in the design of the plant, and that provide assurance that the site is disregarded in the detamination of their radiation status (NBS sits characteristics are==== Ale to the acceptable for the proposed design.
RottormkforindrvidualOfferio
$same I
clearly ev
rotnd lic unta states that the===s=lan's use of this 6
r security meneums to protect the plant.
A. Exclusion Area. An exclusion asua m rm==i=le has also had a long surrounding the i==adame= vidnity of value does not issply that it===idars it 4-readers a the plant has been a requiresnent for to be an arvapaala limit for an from dansA---
centers, and7s siting power reactoss imm the emergency does to the public under f,
standing policy of si antinulag thisimlicy in the proposed beginning/11Is area providesa accident==ditiana but only that it b
rule.
degies of pr=*=retan to the public represents a soference enlue to be used g
m ca==l==lan is propostag to a variety of pan==*1=1 plant =aridane=
for evaluating plaat E=*=== and site incorporate basic reactor site criteria in and also a5ards
- e'a= to the characteristics intended to mitigets the the proposed rule to accomplish the from potentialman.seleted
& radiologicalconesquenons ofh*=
! p above purposes.
c===l==ta= considers an==rbir= area in order to peevida--oflow risk 1
b can= lesion pro to be an eseantiat iestme of a 4 ector site to the public under; "" '
1 source term and does r= poses to retain Imlations to and is proposing to retain this accidents. h r===i=1a= based upon verify the adequacy of a alte for a
='
- - for futmo seedom, extensive --- " = in oppi this -
specific plant, tut source term and does 5+the proposed rule Jesund for criterion,and in senegnition of
]
calculations will be relocated to part 50,
=====t inruaw, seat proposed a conservatimiasthe :
, ' -- in its
^
since experience has shown that these minimum dias=== to the==rbia= area application (alarge Aselon psoduct I
calculations have tended to inDuence boundary of GA salles(840 meters),
release within a =*=ta===*===ardatad plant design aspects audi as bened upon the siaggested value givenin with malercore d==aem==vi===
i containment leek rate or Alter Regulatory Guide 4.7,without =*ilising allowable contoimeentleekrete,a t
i =L,. &.s rather then siting.No source tenn and does eahkia
'I1ds single failuse of any of the
}"
specific sowce tenn would be
. was based upon a conservative on pmductcleanup systsens,such referenced in part so. Rather, the sousco evaluation of the;- i- = of Resion as the==*=8====# spesys, adveese site term would be requimd tobe one that product cleanup systems such as meteorological --
j
^
is "* *
- assumed to result in containrment sprays or Alter syntesis.
characteristics,anindividual H
i substantial meltdown of the core with Numerous -===a= wese seenived to be iomtad at the boundaryinf the j
subsequent release into the m= amin = ant stating that source term and does exclucion ame at the centerline of the
[
j cf cypreciable quantities of flesian c=Wi=*1<== should be retained, and plume for two hours without psetective 3
products." Hence, this guidance could that the archian area distance should actions), believes that this af terian has be utilized with the source term also be bened upon a more r==%*1c clearly s== lead in en adequate level of currently used for light-water readers, evaluation of adual R==lan product protection. As en ilhastation of the 1
or used in conjunction with revised cleanup syne=== la responsa to these conservatism of this assessment, the
a 52258 Federal Register I.Vol. 59, No.199 / Monda3. Octolxn '17, w94 J Proposed Rulos maximum whole body dose received by represent a risk of abut 22x10%
olhohe that the dose to an individual ~
3 at h On excess of 25 rem TEDE for any an actual individual during the Three Umg a rtA coefficxatofh3 Mlle Island accidentin March 1979, per rem, the risk of latent canmr fatalef 'twohnur period after the appearance of which involved mejor core damage, was implied by the cunent de se critada h fissiorcproducts within containment. '
estimated to be about 0.1 rem.
equivalent to 27 rem 77DE. (BEIRV ne Commission is proposing this in the proposed rule,the Commission estimates a latent cancer fatality ri21 change to reflect improved is proposing two changes in this area.
coefficient of about 5x10-* per renCd understanding of fission product release First, the Commission is proposing the dose is received over a period of into the containmant under severe that the use of different doses for the days or more; however,if the exposure accident conditions. For an assumed wholo body and thyroid gland be period is shorter, such aso hours, the instantaneous release of fission replaced by a single value of 25 rem.
risk coefficient is approximately products, as contemplated by the tutal effecuve du:,e equivalent (TEDF).
dvuble.)
present rule, the.two hour period that The total effectivo dose equivalent f latunt cancer lucidence rather than commences with the onset of the fission concept is consistent with part 20 of the fatality were usod, the curmnt dose product release clearly results in the Commission's regulations, and is criteria would correspond to's value of highest dose to a hypothetical defined as the deep dose equivalent (for about 35 rem TEDE.
Individual offsite. Improved external exposures) plus the committed The Commission is proposing to use understanding of severe accidents effective dose equivalent (for internal the risk of latent canar fatality as the shows that fission product releases to exposures). The deep dose equivalent is appropriate risk measuru since the containment do not occur the same as the present whole body quantitative health objectives (QiiOs) instantaneously, and that the bulk of the dose, while the committed effective for it have been established in the releases may not take place for about an dose equivalent is the sum of the Commission's Safety Goal policy.
hour or more. Hence, the two-hour products of doses to selected body Although the current dose criteria are period commencing with the onset of l
organs times weighting factors for each equivalent in risk to 27 rem'ITDE, as lission product release may not organ that are representative of the noted above, the Commission is represent the highest dose that an radiation risk associated with that proposing to use 25 rem TEDE as the individual could be exposed to over any dose criterion for plant evaluation two-hour period. As a result,the j',
- organ,
%e proposed use of the total effective purposes, since this va!ue is essentially Commission is proposing that various dose equivalent, or TEDE,is based upon the sarne level of risk as the current two-hour periods be examined to assure j
two considerations. First, since it criteria.
that the dose to a hypothetical l
utilizes a risk consistent methodology to Nevertheless, the Commission is individual at the exclusion area assess the radiological impact of all specifically requesting comments on the boundary will not be in exass of 25 rem relevant nuclides upon all body organs, use of TEDE. Comments are requested TEDE over any two hour period after the use of TEDE promotes a uniformity and on whether the current dose criteria onset of fission product release.
consistency in assessing radiation risk should be modified to utilize the total B. Site Dispersion Foctors. Site that may not exist with the r.eparate effective dose equivalent, or TEDE, dispersion factors have been utilized to whole body and thyroid organ dose conmpt.%e Comrnission is also provide an assessment of does to an values in the present regulation, requesting comments on whether a mdividual as a msult of a postulated Second, use of 'ITDE lends itself readily TEDE value of 25 rem (mnsistent with accident. Since the Commission intends to the application of updated accident latent cancer fatality), or 34 rem to require that a verl6 cation be made source terms,which can vary not only (consistent with latent cancer that the exclusion area distance is with plant design,but in which incidence), or some other value should adequate to assure that the guideline q
additional nuclides besides the noble be used. Finady, because the thyroid dose to a hypothetical individual will gases ed lodine are predicted to be weighting factor is equal to a value of -
not be exmeded under postulated mioased into containment.
0.03, there exists a theomtical accident conditions, as well as to assure The Commission has axamined the possibility that an accidental release that radiological thnits are met under current doas criteria of 25 rem whole mmposed only of ladina could result in normal operating conditions,the body and 300 rem thyroid with the a TEDE less than 25 rem,yet result in Commission is proposing that the latent of selecting a 'ITDE numerical a thyroid dose of over 800 rem.
atmospheric disponion characteristics Although the 'a==lamian believes that of the site willbe required to be -
r value equivalent to the risk implied by the current does criteria. nese risks the likelihood that an actual accident evaluated, and that site di on consist of tlw risk of developing cancer would release onlyiodineis highly facters based upon this e untion be some time after the exposure (latent unlikely, comments are also requested determined and used in assessing
- cancer incidenm), as well as a delayed - as to whether the does criterion should radiological consequences of normal risk of cancer fatality (latent cancer also include a " capping ~' limitation, that operations as well as accidents.
fatality). For a dcas of 25 rem whole is, an additional requirement that the C. IowPopulation Zone.no present body,the individual risk oflatent.
dose to any individual organ not be in regulation requires that a low cancer fatality is estimated to be about excess of some fraction of the total.
population zone (LPZ)be defined 2.5x10-8; the risk oflatent cancer The somnd change being proposed in Inunediately beyond the exclusion area.
incidence is about twice that (using risk this area is in regard to the time period Residents are permitted in this area, but coefficients expressed by ICRP that a hypotheticalindividualis the number and densig must be such Publication so and in N11 REG /CR-assumed to be at the exclusion area that there is a i:r*=--s probability 4214). For a done of 300 rem thyroid, the boundary. While the duration of the that appropriate protective measures risk of latent cancer fatality is about time period remains at a value of two could be taken in their behalfin the 2x10-*;the risk oflatent canar hours, the Commlanton is proposing that event of a serious accident. In addition, incidence is about a factor of ten higher, this time period not be fixed in regard the nearest denselv populated center If the risk of latent cancer fatality is to the appearance of fission products mataining more t6an about 25,000 selected as the appropriate risk measure within containment, but that various residents must be located no closer than to be used, the current dose criteria two-hour peri:ds be examined with the one and one-third times the outer
Federal Regist:r / Voi.' 59, No. k99 / Monday, October 17. 1994 / Proposed Rules 52259 f
a.
boundary of the LPZ. Finally, the dose smallar than that envieloned far the whether a particular population density to a hypothetial individual' located at exclusion area.
would meet the Safety Goal.
the outer boundary of the LPZ over the G. AdequacyofEmergencyPlans.The flowever, results of severe aafdent entire course of the accident must not be proposed rule would also require that risk studies, particularly those obtained in excess of the dose values given in the the site characteristics be such that from NUREG-1150, can provide useful c
mgulation.
adequate plans to carry out protective insights for considering potential H
13efore 1980,the LPZ generally measures for members of the public in criteria for population density. Severe N
dtfined the distance over which public the event of emergency could be acddents having the highest 4
protective actions were contemplated in developed.
consequences are those where core-melt
'i the event of a serious accident.The II SitiDBAmyFmm Densely together with early bypass of or regulations in 10 CFR 50 47 now Populated Centers. Population density mtal4anent failure owurs. Such an
'i requires phune exposure Emergency considerations beyond the exdusion event would likdyload to a "kge Planning Zones (EPZ) of about 10 miles area have been required since issuance release"(without defining this
'of art 100 in 1962.%e cunent rule precisely). Based upon NUREG-1150, for each plant.
P While the nmmiadon considers that requires a " low population zone"(LPZ) the probability of a core-melt accid at e
the siting functions intended for the beyond th'e immediate exdusion area.
together with early conh inment failure LPZ, namely, a low density of residents The LPZboundary must be of such a or bypass for some current generatioe and the feasibility of taking protective size that an individual located at its LWRs is estimated to be between to-s cctions,have been accomplished by outer boundary must not recalve a dose and 10-* per reactor year. For future other regulations or can be in excess of the values given in part _100 plants, this value is expeded to be la a cecomplished by otherguidance, the over the course of the acddent.While
- to 4 per reactor year.
commiolon continues to believe that a numerical values of populat!m a If a reador was located nearer to a j
requirement that limits the radiologimi Population density am not specified for large city than current NRC practice
. i consequences over the course of the this regin, the regulade also mquires nermitted, the likelihood of exposing a d
l nccident provides a useful evaluation of that the nearest boundary of c densely large number of people to significant M
the plant's long-term capability to moulated center of about 25,000 or releases of radioactive material would N
i mitigate postulated acddents. For this more persons be located no closer than be about the same as the probability of M
reason, the %==8-fon is proposing io one and one-third times the LPZ outer
.a.
.a ~9y containment k
r retain the requirement that the dose.
bandary. Part 100 has no populatim failure,that is, less than to-*
r E
reactor year for future reactor gns. It N
consequences be evaluated at the outer criteria other than the size of the LPZ boundary of the LPZ over the course of and the proximity of the nearest is worth noting that events having the
?
ths eht accident and that these Population center, but notes that "whem very low likelihood of about 10"per f
not be in excess of 25 rum TEDE.
very larBe dtles are involved, a greater reactor year or lower have been mgarded I
D. Physica!Chmuderistics of the Site. distance ma be necessary."
in past licensing actions to be Whereas exclusion ama size is It has been requimd that physical
" incredible", and as such, have not been characteristics of the site, such as the based upon limitation ofindividual risk, required to be incorporated into the -
Eeology, seismology, hydmlogy, Population density requimments serve design basis of the plant. Hena, based s
meteoro!
characteristics be to set sodetal risk limitations and relled solely upon accident likelihood,it consi in the design and cmsidention daaddents beyed the might be ed that siting a mactor T
construction of any plant posed to be design basis, or severe accidents. Such nearer to a dty than current NRC d'
I located them.ne rule wodd acddents were clearly a consideration -
pudimwoul posenoundW.
require that these stics be in the original 1-=== d part 100, If, however, a reactor were sited away V
evaluated and that sita parameters, such frora large dties, the likelihood of the N
since the Statement of Considerstims as design basis flood conditions or (27 FR 3509; April 12,1962) noted that: dty being affected would be redumd tornado wind loadings be established Further, since accidents of greater potential because of two factors. First,because the for usein evaluating any t to be he-i then those --ly seWd **
windis expected to blow in all located on that site in to ensure mPresenting an upper limit are conostveble, directions with roughly the same that the ocx:urrence of sudi physical
%f "g**,
frequency,thelikelihood that honomena wouki pose no undue prmection noessiw exposure doses radianctive material would actually be to people in centers, when ettective carried towards the dtyis reduced E.Neorby nunsportorion Routes,.
preactin measume misht not be leasible significantly because it is likely that the IndustnialandMilitaryFadfities. As for * *
- Henca,thepopulation omterdistance wind willblow in a diredian away imm natural phenomena, it has been a long-was added as a site aquhunent the dty. Second, the radiological dose standing NRC staff predios to aview Limitation of population density b4 m -
es would alsobe reduced man-related activities in the site vicinity the exclusion area has the following with distance because the radioacthe t2 provide assurance that potential benefits.
material becomes increasingly diluted hazards -Mated with suda facilities (a)It fadlitates emergency by the a are and the inven or transpostation routes will pose no preparedness and planning: and '
becomes d due to the nat undue riskto any plant proposed to be t'b) It reducas potontial doces to large processes fallout and reinoutbefore losted at the site. ne x.y.wd rule nun bers of people and reduces property reaching the city. Analysse indicate that would codify this ca.
damane in the event of severe acddents. if a reactor were located at distances F. AdequocyofSecurityPfans.%e Altliough the Cn==hton's Safet ranging imm to to about 20 miles away proposed rule would requim that the Goal policy provides guidance on* y from a dty, depending upon its size. We characteristics of the site be such that individual risk limitations,in the form likelihood of exposure of large numba 3 adeguate security plans and measures of the Q.antitative Health Objectives of le within the dty would be t
for tne plant muld be developed.%e (QHO),it provides nu guidance with uced by fadors of ten to one hundred
(
Commissien envisions that this would regard to societal risk limitations and or more compared with locating a 4
cat:ll a small secure area considerably therefore cannot be used to ascertain reactor very close to e city.
I
l 52260 Fedrl Register / Vol. 59, No.199 / Monday, October 17. 1994 / Proposed Rules 1
1 In summary, next-generation re ctors things, that "the central lows nuclear centers, including " major" population are experied to have risk characteristics project and other reactors be sited at centers, depending upon their size, that sufficiently low that the safety of the least 40 miles from major populatien would hmit societal consequences
.}
public is reasonably ossured by the centers." The petitioner also stated that significantly,in the event of a severe j
reactor and plant design and operation
" locating reactors in sparsely. populated accident. The Commission finds that l
itself, resuhing in a very low likelihood areas * *
- has been endorsed in non.
granting of the petitioner's request to j,
of occurrence of a severe amident. Such binding NRC guidelines for reactor specify population criteria out to 40 h
a plant can satisfy the Qllos of the siting." The petitioner did not specify miles would not substantially reduce i
Safety Goal with a very small exclusion what constituted a major population the risks to the public. As notod, the area distance (as low as 0.1 miles). The center. The only NRC guidelines Comioission also believes that a higher 1
l consequences of design basis accidents. concerning population density in regard population density site could be found analyred using revised murre terms and to rwtor siting are in Regulatory Guide to be acceptable, compared to a lower j
with a realistic evaluation of engineered 4.7, issued in 1974, and revised in 1975, population density site, provided there D
safety features, are likely to be found prior to the date of the petition. This were safety, environmental or economic acceptable at distances of 0.25 miles or guide states population density values advantages to the higher population site.
j less. With regard to population density of 500 persons per squam mile out to a Granting of the petitioner's request J
beyond the exclusion area, siting a distance of 30 miles from the reactor, would neglect this possibility and i
i reactor closer to a densely populated not 40 miles.
would make population density the sole city than is current NRC practice would Regulatory Guide 4.7 does provide criterion of site acceptability. For these
]
pose a very low risk to the populace.
effective separation from population reasons, the Commission has decided
,l Nevertheless, the Cornmission centers of various sizes. Under this not to adopt the proposal by Free considers that defense in-depth guide, a popuh. tion center of about Environment, incorporated.
]
considerations and the additional 25,000 or more residents should be no The Commission also notes that
{
1 l l enhancement in safety to be gained by closer than 4 miles (6.4 km) from a future population growth around a siting reactors away from densely reactor because a density of 500 persons nuclear power plant site, as in other j
populated centers should be per square mile within this distance areas of the region is expected but j
maintained.
would yield a total population of about cannot be predicted with great accuracy, The Commission is proposing a two-25.000 persons. Similarly, a city of particularly in the long-term. Since tier approach with regard to population 100,000 or more residents should be no higher population density sites are not density and reactor sites. The proposed closer than.about to miles (16 km); a unacceptable, per se, the Commission rule states that reactor sites should be city of 500,000 or more persons should does not intend to consider limnse located away from very densely be no closer than about 20 miles (32 conditions or restrictions upon an populated cer.ters, and that areas of low km), and a city of 1,000,000 or more operating reactor solely upon the basis population density are, generally, persons should be no closer than about that the population density around it preft:Ted. The Commission believes that 30 miles (50 km) from the reactor.
may reach or exceed levels that were not a site not falling within these two The Commission has examined these expected at the time of site approval.
categories, although not preferred, could guidelines with regard to the Safety Finally,the Commission wishes to l
be found acceptable under certain Goal.The Safety Goalquantitative emphasize that population conditions.
health ob}ective in regard to latent considerations as well as other siting j
J The Commission is not establishing canar fatality states that,witidn a requirements apply only for the initial specific numericalcriteria for distance of ten miles (to km) from the siting for new plants and will not be b
evaluation of population density in reactor, the risk to the population of used in evaluating applications for the siting future reactor fr.cilitied -..
lAnt canccr fatality from nuclear renewal of existing nuclear power plant the acmptability of a specific alte from power plant operation, including licenses.
the standpoint of population density accidents, should not axmed one" tenth 4
i' must be considered in the overall of one percent of the likeuhood oflatent Change to 10 CFR Part 50 J
l {
context of safety and environmental cancer fatalities from all other causes. In ne proposed change to 10 CFR part j-considerations.no Commission's addition to the risks of latent cancer 50 would relocate from to CFR Part 100 intent is to assure that a site that has fatalities, the Commission has also the dose requirements for each significant safety, environmental or investigated the likelihood and extent of applicant at specified distances.
economic advantages is not rejected land contamination arising from the Because these requirements affect solely because it has a higher release of long lived radioactive species. reactor design rather than siting. they population density than other available such as ceslum-137,in the event of a are more appropriately located in to sites. Population density is but one -
severe reactor accident.
CFR part 50.
f
! actor that must be balanmd against the ne results of these analyses indicate These requirements would apply to other advantages and disadvantages of a that the latent cancer fatality future applicants for a construction particular site in determining the site's quantitative health objective noted permit, design certification, or an acceptability.%us,it must be above is met for current plant designs.
operating license. %e Commission will recognized that sites with higher From analysis done in support of this consider after further experiena in the I
population density, so long as they are proposed change in regulation,the review of certified designs whether located away from very densely hkelihood of peimanent relocation cf more specific ents need to be populated centers, can be approved by people located more than anout 20 miles developed reg ng revised accident the Comminionif they present (50 km) from the reactor as a result of source terms and severe accident l
advantagesin terms of other land contamination from a severe insights.
considerations applicable to the accident is very low.
B. Seismic ond Earthquale Engineering Therefore, the Commission concludes evaluation of proposed sites.
that the current NRC staff guidance in Meria On April 28,1977, Free Environment, Inc. et al., filed a petition for rulemaking Regulatory Guide 4.7 provide a means of The following major chages in the locating roactors away from population proposed revision to Appendix A.
(PRM-50-20) requesting, among other' R
l
I 1
a Fed:r:1 Register / Vol. 59, No.199 / Monday, October 17, 1994 / Proposed Rules 522G1 a
.a
" Seismic and Geologic Siting Criteria necessary when more complete single set of earthquale sources, i,
for Nuclear Power Plants," to part 100, infonnation becomes available.
develops for each source a postulated
,A e.re associated with the proposed liowever, haviu8 6coscicaco uthquake to La used as the souscu of Il I
seismic and earthquake engineering assessments detailed and cast in a ground motion that can affect the site,
.I criteria rule making. These changes regulation has created difficulty for locates the postulated earthquake 1
reflect new information and research applicants and the staffin tenns of according to prescribed rules, and then results, and incorporate the intentions inhibiting the use of needed latitude in calculates ground motions at the site.
of this regulatory action as defined in judgment. Also,it has inhibited Although this approach has worked Section til of this proposed rule flexibility in applying basic principles reasonably well for the past two'
.t including cmnments from the public on to new situations and the use of decades,in the sense that SSEs for i
the first proposed revision of the evolving methods of analyses (for plants sited with this appmach are regulations. A specific document instance, probabilistic) in the licensing judged to be suitably conservative, die approach has tiot e:xp!!cidy ruu>gnized explaining the NRC staff's disposition of pmcess.
pertinent comments will be prepared The pwpo.wd regulation would be uncertaintics in goosciences parametcrs.
coincident with the final rulemaking.
streamlined, becoming a new section in Because so little is known about
- i Subpart B to 10 CFR part 100 rsther earthquake phenomena (especially in
[
- 1. Separate Siting From Dastgn than a new appendix to part 100. Also, the eastem United States), there have the level of detail presented in the often been differences of opinion and Criteria not associated with site PNPosed regulation would be reduced differing interpretations among experts suitability or establishment of the Safe considerably. This approach reflects the as to the largest earthquakes to be j
Shutdown Earthquake Ground Motion philosophy of the first proposed considered and ground-motion models (SSE) have been placed into 10 CFR part revisi n that the regulation only to be used, thus often making the
{
- 50. This action is consivent with the c ntains the basic requirements and that licensing process relatively unstable.
l location of other. design requirements in the detailed guidance, which is Over the past decade, analysis g
10 CFR part 50. Because the revised contamed in the current regulation, methods for incorporating these j
criteria presented in the p sed Appendix A to 10 CFR part 100, be different interpretations have been
.!f lation will not be a to and used.These removed to guidance documents. Thus, developillstic" methods have been ting plants, the lice ing basis for the pmposed regulation contains:(a)
"probaa g
existing nuclear power plants must R uired definitions,(b) A requWment designed to allow explicit incorporau,on
-)
remain part of the regulations.The to etermme the goological.
of different models for r.onation, criteria on seismic and geolog,ic siting seism I gical, and engineen,n eartnquake size, ground motion, and would be designated as a new $ 100.23 characterisucs of dw repos site, and other parameters. The advantage of to subpart B in 10 CFR part 100. Criteria (c) A requirement to etennine the Safe using these probabilistic methods is on earth uake en8 neering would be Shutdown Earthquake Ground Motion their ability to not ont incorporate 9
i (SSE) and its uncertainty, to determine different models and ifferent data sets, ynhec^dn at a
PP a for the potential for surfam deformation, but also to weight them using judgments Nuclear Power I,lants,,,8to 10 CFR partand to determine the design bases for as to the validity of the different models 9
50.
seismically induced floods and water and data sets, and thereby providing an
- 2. Remove Detailed Guidance From the waves.The guidance documents explicit expression for the uncertainty Regulation describe how to carry out these required in the ground motion estimatos and*a determinations.The key elements of the meansof assessingnensitivit to various The cunent regulation contains both balanced approach to determine the SSE input parameters. Another a vantage of requirements and guidana on how I are presented in the following section.
the probabulstic method is the target satisfy Ge requirements. For example.
The elements are the guldence that will exceedance probability is set by Secdon W," Required Investigadons,"
be fully described in the guidance examining the design bases of more cf Appendix A, states that im estigations documents. The proposed regulation is recently limnsed nuclear power plants, are required for vibratory g mind.
a new section in part 100 rather than an The proposed revision to the motion, surfam faulting, and seismically appendix to Part 100.ne proposed regulation now explicitly ra-i-induced floods and water waves.
regulation would identify and establish that there are inherent uncertainties in Appendix A then provides detailed basic requirements. Detailed guidance, estabbhing the seismic and geologic guidance on what constitutes an that is, the procedures a<xieptable to the design parameters and allows for the i
acceptable investigation. A airnib' NRC for meeting the requirements, option of using a probabilistic seismic situation exists in Section V,"Scismic would be contained in a draft regulatory hazed methodology capable of a
and Geologic Design Bases," of guide to be inued for public comment propagating unartainties as a means to Appendix A.
as Draft Regulatory Guide, DG-1032,.
address theso im-tainties.The rule Geoscience assessments require "IdentiBcation and Characterization of further regni-that the nature of considerable latitude in judpnent. This Seismic Sources and Determination of uncertainty and the appmpriate latitude in judgment is needed because Safe Shutdown Earthquake Ground approach to amount for it depend of limitations in data and the state-of-Motions."
greatly on the tectonic regime and paratneters, such as, the knowledge of the-art of geologic and seism!.: analyses
- 3. Uncertainties and Probabilisti:
,,g,:mic sources, the existence of and because of the rapid evolution Me' hods historical and recorded data, and the taking place in the geoscienms in terms cf accumulating knowledge and in.
ne existing approach for determining understanding of tectonics.Therefore, modifying concepts.This need appears a Safe Shutdown Earthquake Ground methods other than the pmbabilistic to have been recognized when the Motion (SSE) for a nucl6ar reactor site, methods, such as sensitivity analyses, cxisting regulation was developed. %e embodied in appendix A to 10 CFR part ' may be adequate for some sites to existing regulation states that it is based 100, relies on a " deterministic" acx:ount for uncertainties.
~
cnlimited eoP ysicalandgeological approach. Using this deterministic ne NRC staff has achieved an B
h information and willbe revised as approach, an applicant develops a appropriate balanm between
l 52262 Federal Regist:r / Vol, 59, No,199 / Mondly, October 17. 1994 / Proposed. Rules deterministic and prohibilistic seismic regulation are described in Draft
- 5. Value of tha Operating Btsis ha-ard evaluations to be used in the Reculatory Guide DG-1032, Earthquake Ground Motion (OBE) and revision of the seismic and geologic
" Identification and Characterization of Required OliE Analyses j].
sitin criteria for nuclear power plants.
Seismic Sources and Determination of The existing regulation (10 CFR, The eyelementsof thisbalanced Safe Shutdown Earthquake Ground appendix A, section V(a)(2)) states that appmach are.
Motions."
the maximum vibratory ground motion
-Conduct site-specific and regional The NRC staffs review anproach to of the OBE is at least one half the 1
j g oscience investigations
- cvaluate an application is described in maximum vibratory gmund motion of l
.l e
p bability is set Draft SRP Section 2.5.2. This review the Safe Shutdown Earthquake ground by takes mto account the information base motion. Also, the existing regulation (10 more recently licensed nuclear power developed in licensing more than 100 CE R, appendix A, section VI(a)(2)) states
%'ct probabilistic seismic hazardpL ats. Thi:n,taff review is consistent that the engineering method used to y
)
ondu mda tho intent of a USGS insure that structures, systems, and recommendation. Althoughthebasic components are capable of withstanding j
1 analysis and determine und the effects of the OBE shallinvolve the j,
motion level correspon g to the premise in establishing the target I!
target exceedance probability, cyceedance probability is that the use of either a suitable dynamic analysis
!l
-Determine if infonnation from current design levels are adequate, a
, or a suitable qualification test. In some i
geoscience investigations change staff review further assures that there is cases, for instance piping, these multi-i
-Determine site-specific spectral shape mnsistency with previous limusing facets of the OBEin the existing probabilistic results, and scale this shape to the ground decisions and that the scientiSc basis regulation made it possible for the OBE J
motion level determined above, for decisions are clearly understood.
to have more design significana than
-NkC staff review using all available This review approach will also assist in the SSE. A decoupling of the OBE and data including insights and assessing the fairly comr ax regional SSE has been sug<;ested in several f
p documents. For instance, the NRC i,taff, information from previous licensing probabilistic modeling which experience, and incorporates multiple hypotheses and a SECY-79-300, suggested that design for
-Update the data base and seassess mu!titude of parameters. Fwthermore, a single lhniting event and inspection and evaluation for earthquakes in excess probabilistic methods at least every' this process should provide a clear basis of some specified Ihnit may be the most ten years.
for the staffs decisions and facilitate sound regulatory approach.NUREG-Thus,the propord approach requires communication with nonexperts, 1061," Report of the U.S. Nuclear thorough regionaland site-specific
- 4. Safe Shutdown Earthquake Regulatory Commission Piping Review geoscience investigations. The proposed Committee," Vol. 5, April 1985. (Table approach reflects some of the comments The existin lation (to CFR part 10.1) ranked a decoupling of the OBE of the U.S. utility industry.The U.S.
100 a section V(a)(1)(lv))
and SSE as third out of six high priority ndix A' mum vibratory Geological Survey provided a series of stat e maxi changes. In SEW 66, comments and recommendations that accelerations of the Safe Shutdown
" Evolutionary Light Water Reactor led to and can be met by the above Earth uake at each of the various (LWR) Certification Issues and Their 9
integrated a[tbmach.e regional and site-I undation locations of the nuclear Relationship to Current Regulatory Results o
- *,8g site Requirements," the NRC staff states that 1
EI specific investigations must be Qgdd ed it agrees that the OBE should not control consideredinap licationof the I cation of the seismic input motion of afd sysms, b dai@es equiv lent to OBE-SSE probabilistic me od.The current control point as stated in the existing Acuv probabilistic methods,the NRC ngulation ha led to confrontations decoupling are also being done in sponsored study conducted by With mad 7 *PP cants thatbulleve this foreign countdes.For instance,in li Lawrewe Uvermore National stipulation is inconsistent with good Germany their new design standard Laboratory (LINL) or the Electric Power engineedng fundamentals.
requires only one design basis Research lastitute (EPR4 esismichazard ne proposed regulation would move. earthquake (equivalent to the SSE).
study, are essentially regional studies the location of the seismic input motion They require an inspection level without detailed information on any specific location. %e regional and site-control point imm the foundation-level earthquale (for shutdown) of to the hoo. field at the free gmund This level was set so that the vibratory l
specific investigations provide detailed information to update the database of surface.The 1975 version of the gmund motion should notinduce the hazard methodology to make the Standard Review Plan pleosd the stresses===At=> the allowable stresa
~
controlmotion in the free field.De limits originally required for the OBE i
i probabilistic analysis site-specific.
proposed regulation is also consistent
- design, Itis also necessary toincorporate local site geological factors such as with the resolution of Unresolved Safety ne proposed mgulation would allow stratigraphy and phy and to Issue (USI) A-40. " Seismic Design the value of the OBElo be est at (i) one.
account for site-s geotechnical Criteria"(August 1989) that resultedin third orless of the SSE where OBE properties in lishing the design the revision of Standard Review Plan requirements are satisfied without an basis ground motion. In order to Sections 2.5.2,3.7.1,3.7.2, and 3.7.3.
explicit response or design analyses incorporata local site factors and However, the proposed regulation being performed. or (ii) a value greater advances in ground motion attenuation requires that the horirontal corapenent than one-third of the SSE, where -
of the Safe Shutdown Earthquake analysis and design are required.There models, ground motion estimates are Ground Motion in the free-Beld at the are two issues the applicant should determined using the procedures outlined in the Draft Standard Review foundation level of the structures must consider in selecting thevalue of the Plan Section 2.5.2, Second Proposed be an appropriate response spectrum OBE: first, plant shutdown is required if Revision 3," Vibratory Ground Motion." considering the site gectechnical vibratory gmund motion eraadl5 that Methods acceptable to the NRC staff properties, with a peak gmund of the OBE occurs (discussed below in for implementing the proposed acceleration of at least 0.1g.
Item 6. Required Plant Shutdown), and i
~
i Federal Regist:r / Vol. 59, No.199 / Monday, October 17, 1994 / Proposed Rules 52263
},
second, tha cmount of analyses Reactor (ALWR) Designs, dated July 21, appendix A to 10 CFR pIrt 100.%is 7
[j limitation requires that if vibratory associated with the OBE. An applicant 1993.
mnv determina that at one-third of the There are situations associated with ground motion exceeding that of the SSE level, the probability of exceedmg current analyses where only otilus oliE occurs, shutdown of the nudear ths OBE vibratory ground motion is too associated with the design power plant will be required. Prior to f
requirements, for example, the uhimate resuming operations, the limnsee will
[4 high, and the cost associated with plant heat sink (see Regulatory Guide 1.27, be required to demonstrate to the shutdown for inspections and testing of " Ultimate lleat Sink for Nuclear Power Commission that no functional damage p
equipment and structures prior to Plants"). In these situations, a value has occurred to those features necessary r, (
restarting the plant is unacceptable.
nerefore, the applicant may voluntarily expressed as a fraction of the SSE for continued operation without undue y'
select an OBE value at some higher resppnw w uld be used in the analyses. risk to the health and safety of the s
Section Vill of this propuxxl rule public." At that time,it was the fraction of the SSE to avoid plant identifies existmg guides that would be intention of the Commission to treat the shutduwus. Ilowewr,if an wpplicant revised technically to maintain tbc Operating Basis Earthquake as a limiting e
selects an OBE value at a fraction of the existing design philosophy.
condition of operation. From the SSE higher than one-third, a suitable In SECY-93-087,"Pohey, Technical, statement in the Supplementary enalysis sball be performed to and Licensing issues Pertaining to information, the Commission directed,
demone. rate that the requirements Evolutionary and Advance Light-Water applicants to specifically review 10 CFR essociated with the OBE are satisfied.
Reactor (ALWR) Designs," the NRC staff Part 100 to be aware of this intention in The design shall take mto account soil-requested Commission approval on 42 complying with the requirements of to structure interacGon effects and the technical and policy issues pertaining to CFR 50.36. Thus, the requirement to expected duration of the vibratory either evolutionary 1.WRs, passive shut down if an OBE occurs was ground motion. The requirement LWRs, or both. The issue pertaining to emected to be implemented by being associ.ted with the OBE is that all the elimination of the OBE is design:*.
mciuded among the technical structures, systems, and components of I.M. The NRC staffidentified actions specifications submitted by applicants the nuclear power plant necenary for necessary for the design of structures, after the adoption of Appendix A. In continued operation without undue risk systems, and components when the OBE fact, applicants did not include OBE to the health and safety of tl e public Dsign requirement is eliminated. The shutdown requirements in their
.i shall remain functional and sithin
.,~ff clarified that guidelines should be technical specifications.
,j epplicable stress, strain and deformation maintained to ensure the functionality The proposed regulation would treat limits when subjected to the effects of of components, equipment, and tb*
9 Ah anociated with the OBE in combination with normal supports. In addition, the staff clarified vibratory ground motion exceeding the operating loads.
how certain design requirements are to OBE or significant plant damage as a be considered for buildings and condition in every operating license. A As stated above,it is detennined that structums that are currendy designed new $ 50.54(if) would be added to the if an OBE of one-third of the SSE is f r the OBE, but not the SSE. Also,the regulations to require a procesa leading used, the requirements of the OBE can NRC staff has evaluated the effect on to plant shutdown for h,censees of ba satisfied without the applicant safety f eliminating the OBE from the nuclear power plants that comply with rf H
design load combinations for selected the earthquake engiacering critoria la alyses la th s c7se structures, systems, and components Paragra hIV(s)(3)of Proposed BE rves ths function of an inspection and and I as developed proposed criteria for Appen tx S " Earthquake Engbeering shu.tdown earth uake. Some minimal an analysis using on1 the SSE.
Critena for Nuclear Powe t'lants," to 10 9
Commission approvafis documented in CFR part 50. Immediate shutdown could design checks and, the a licability g the Chilk to Taylcr memorandam dated be required untilit is detar=In-i that s pos o se s
) g8 July 21,1993, cited above.
structures, systems, and cornponents high confidence that, at this ground-More than one earthquake response needed for safe shutdown are still I
motion level with other postulated analysis for a seismic base isolated hincuonal.
wncurrent loads, most critical nuclear power plant design may be Draft Regulatory Guide DG-1034, stmetures, systems, and comoonents necessary to ensure adequate
" Pre-Earthquake Planning and
)
will not exceed currently used design performance at all earthquako levels.
Immediate Nuclear Power Plant limits. Ris is ensured. in part, bemuse Decisions pertaining to the response Operator Post-Earthquaka Actions,"is (y, )
PRA insights willbe used to support a analyses associated with base isolated being developed to provide guirlanem 1
margins type assessment of seismic facilities will be bandled on a case by acceptable to the NRC staff for determining whethat or not vibratory.
events. A PRA based seismic margins case basis, analysis will consider esquence-level ground motion exceeding the OBE High Confidence, Low Probability of
- 6. Required Plant Shutdow ground motion or significant plant' Failures (HCLPFs) and fragilities for all ne current regulation (section
<inme had ocx:urred and the timing of sequenasleading to core damage or V(a)(2)) states that if vibratory ground nuciear power plant shutdown.%e containment failures up to motion exceeding that of the OBE guidance is based on criteria developed approximately one and two-thirds the occurs, shutdown of the nuclear power by the Electric Power Research Institute ground motion acceleration of the plant is required.%e supplementary (EPRI).ne decision to shut down the design basis SSE (
Reference:
Item II.N, information to the final regulation plant should be made within eight She-Specific Probabilistic Risk (published Ilovember 13,1973: 78 FR hours after the earthquaka.%e data Assessment and Analysis of External 31279, item 6e) includc: the following from the seismicinstrumentation, Events, memorandum from Samuel J.
statement:"A footnote has~been added coupled with information obtained from Chilk to James M. Taylor,
Subject:
to $ 50.36(c)(2) of 10 CFR part 50 to a plant walk down, are used to make the SECY-93-087-Policy Technical,and assure that each power 1.lant is aware of determination of when the plant should Licensing issues Pertaining to the limiting condition of operation be shut down, ifit has not already been Evolutionary and Advance Light. Water which is imposed under section V(2) of shut down by operational perturbations
52264 Feder:.1 Regist:r / Vol. 59, No.199 / Monday, October 17, 1994 / Proposed Rules
- 7. Draft Standard Review Plan Section resulting from the seismic event. The part 50 definidor.s with reference to guidance being developed in Draft both the part 100 and part 50 dose 2.5.3, Proposed Revision 3 "Surfico Regulatory Guide DC-1031 is bsed on guide!!nes.
Faulting."The draft decribns promdures to assess the adequacy of the two assumptions, first, that the nuclear VI. Related Regulatory Guides and applicant's submittal related to the power plant has operable seismic Standard Review Plan Section existence of c potential for surface mstrumentation, including the The NRC is developing the following
- faultin6 affecting the site.
equipment and software required to draft regulatory Euides and standard
- 8. DG-4003, Second Proposed promss the data within four hours after review plan sections to provide Revision 2 to Regulatory Guide 4.7, an earthqugke, and second, that the prospective licensees with the necessary " General Site Suitability Criteria for operator walk down inspections can be guidance for implementing the Nuclear Power Plants " his guide performed in approximately four to eight hours depending on the number of proposed regulation. The notice of discusses the major site characteristice availability for these mat erials will be related to public health and safety end i
The regulation also includes a provision published in a later imm of the Federal environmental issu perr.onnel conducting the inspm. lion.
i considers in determining the suitability I
that requires the licensee to consult Register.
- 1. DG-1032," Identification and of sites.
with the Commission and to propose a Characterization of Seismic Sources and VII. Future Regulatory Action I
plan for the timely, safe shutdown of the Determinadon of Shutdown Earthquake nuclear power plant if systems, Ground Motions." The draft guide Several existlng regulatory guides will structures, or components necessary for provides general guidance and be revised to incorporate editorial a safe shutdown or to maintain a safe recommendations, describes acceptable changes or maintain the existing design shutdown are not available. (This Procedures and provides a list of or analysis philosophy.These guides unavailability may be due to earthquake reforences that pescut acceptable will be issued subsequent to the
?
related damage.)
methodologies to identify and publication of the final regulations that Draft Regulatory Guide DG-1035, would implement this pmposed action.
" Restart of a Nuclear Power Plant Shut characterize capable tectonic sources The folfowing regulatory guides will Down by a Seismic Event." is being and seimgenic sources.Section V.B.3 be revised to incorporate editorial developed to pmvide guidelines that are of this Proposed rule describes the key changes, for example to reference new elements.
1 acceptcb!s to the NRC staff for
- 2. DG-1033. Third Proposed Revision sections to part 100 or appendix S to performing inspections and tests of 2 to Regulatory Guide 1.12," Nuclear part 50. No technical changes will be j
nuclear power plant equipment and Power Plant Instrumentation for 1.1.57," Design Ilmits and loading saade in these regulatory guides.
iI structures prior to plant restart. This Earthquakes." The draft guide describes Combinations for Metal Primary Reactor guidance is also based on EPRi reports.
seisinic instrumentation type and Contatnment System Components."
Prior to resuming operations, the location, operability, characteristics, 2.1.59," Design Basis Fioods for licensee must demonstrate to the Commission that no functional damage installation, actuation, and maintenance Nuclear Rower Plants."
that are aw.optable to the NRC staff.
3.1.60," Design Response Spectra for has ocx:urred to those features necessary
- 3. DG-1034," Pre Earthquake risk to the healt and safety of the Planning and immediate Nuclear Power Piants., Design of Nuclear Pow for continued o ration withcat unde Seismic public.Re resul5 of post-shutdown Plant Operator Post-Earthquake 4.1.83,, inservice Inspection of Actions."no dran guide provides Pressurized Water, Reactor Steam inspections, operability checke, and l
surveillance tests must be documented guidelines that are acceptable to the T
Ge N' t l
in written reports and submitted to the NRC staff for a timely evaluation of the 5
2
- Co inI"8 Modal R and Spa *1al Compon,ents in Se recorded seismic instrumentation data ismic Director, OfDm of Nuclear Rearw and to determine whether or not plant
" * ' ^
i Regulation.%e licensee shall not
' mtedion for resume operation until authorized to do shutdown is p* Restart of a Nuclear P
2 Nuclear Power Plants [PluEging
- 4. DG-1035, so by the Director.OfSee of Nuclear Power Plant Shut Down by a Seismic 7.1.121, ** Bases fo Reactor Regulation.
Event"ne dra.ft guide provides Degraded PWR Steam Gene ator Tubes."
- 7. Clarify Interpretations guidehnes that are acceptable to the 8.1.122." Development of Floor In $ 100.23 to 10 CFR part 100, NRC staff for performinginapedions Design Response Spectra for Seismic changes have been made to resolve and tests of nuclear power plant Design of Floor. Supported Equipment huipment and stmetures prior to nestart ents?
or Co*howing regulatory guides will questions ofinterpretation. As an a plant that has been shut down ne f example, definitions and required investigations stated in the proposed because of a seismic event.
be revised to update the design or
- 5. Draft Standard Review Plan Section analysis philosophy, for example, to regulation would be significantl 2.5.1, Proposed Revision 3," Basic change OBE to a fraction of the SSE:
changed to eliminate or modify hrases Geologic and Seismic Information."-%
1.1.27," Ultimate Heat Sink for that were more applicable to o y the draft describes prradures to assess the Nuclear Power Plants."
westem part of the United States.
adequacy of the Seologic and seismic Electric and Mechanical Equipment for-2.1.100," Seismic Qualification of The institutionaldefinition for
" safety-related structures, systems, and information cited in support of the cornponente" is drawn from appendix A applicant's conclusions concerninE theNuclear Power Flants."
3.1.124 "Servicelimits andleading to part 100 under III(c) and Vl(a). With suitability of the plant site.
th proposed relocation of the
- 6. Draft Standard Review Plan Section Combinations for Class 1 Linear-Type earthquake engineering criteria to.
2.5.2, Second Proposed Revision 3 Component Supports."
4.1.130," Service Ilmits and Imading appendix S to part 50 and the proposed " Vibratory Ground Motion." The draft Combinations for Class 1 Plate-and.
relocation and modification to dose describes pmcedures to assess the Shell. Type Component Supports."
guidelines in S 50.34(a)(1), the ground motion potential of seismic 5.1.132," Site Investigations for definition of safety-related structures, sources at the site and to assess the Foundations of Nuclear Power Plants."
systems, and components is included in adequacy of the SSE.
l i,
Federal Register / Vol. 59, No.199 / Monday, October 17, 1994 / Proposed Rules 52265 G.1.138,*' Laboratory Investigations of electronic format on 5.25 or 3.5 inch equipmint, and piping, and with 1
Soils for Engineering Analysis and computer diskette; IBM PC/ DOS or MS/ maintenance of seismic Design of Nuciaer Power P! Ants."
DOS format. Data files should be instrumentation. Base line inspections n
are needed to differentiate between pre-i 7,1.142," Safety-Related Concrete provided in one of the following Structures for Nuclear Power Plants formats: Wordperfect, IBM Document existing conditions at the nuclear power
{[i (Other than Reactor Vessels and Content Architecture / Revisable-Form.
plant and earthquake related damage.
Containments)."
Text (DCAIRFT), or unformatted ASCII The structures, equipment and piping
[
8.1.143, *' Design Guidance for code.%e format and version should be selected for these inspections are those b
Radicadive Waste Management identified on the diskette's external routinely examined by plant operators p[
during normal plant walkdowns and Systems, Structures, and Components
- label, inspections. Routine maintenance of Installed in Light. Water-Coolod Nuclear X. Questions seismic instrumentation ensures its 3
Power Plants."
Minor and conforming changes to In addition to soliciting comments on operability dudag eartacuekes.The i
other Regulatory Culdes and standard all aspects of this rulemaling, the location of the seismic inmunentation review plan sections as a r9sult of Commissios specifically requests is similar to that in the existing nuclear pmposed changes in the nonseinnic comments on the following questions, power plants.The proposed amendments do not affect criteria are also lanned. If substantive A. Nonsea. sink Criteria nonradiological plant effluents and have
,l changes are ma e during the revisions.
- 1. Should the dose acceptance criteria no other environmentalimpact.
ths applicable guides will be issued for be modified from 25 rem whole body The environmental===== ment and
' public comment as draft guides.
and 300 rem to the thyroid to utilize the finding of no significantimpact on t
VIIL Redemeced nac====ts concept of total effective dose which this determination is based are
<l An laterested person may examine or equivalent (TEDE). and if so, what TEDE available for inspection at the NRC
,)
obtain copies of the documents value should be adoptedf Public Document Room 2120 L Street i
referenced in this proposed rule as set
- 2. Assuming that a dose acceptance NW. (Lower level), Washington, DC.
.j criterion of 25 rem total effective dose Single copies of the environmental Copies of NUREG-0625, NUREG-equivalent (IEDE) is adopted, should an assessment and finding of no significant
{
out below.
1150, and NUREG/CR-2239 may be organ limitation or " capping" dose be
~ impact are available from Mr.1Aonard 4
purchamad ime the Superintendent of included, and if so, what should such a Soffer, Offim of Nuclear Regulatory l
Documents, U.S. Government Printing limit bet Research, U.S. Nuclear Regulatory
.J Cor nlasion. Washington, DC 20555, i
Office, Mail Stop SSOP, Waalington, Xt. Finding of No Significant telebone (301) 4154574, or Dr. Murphy,Of h
i DC 20402-9328. Copies are als EnvimamentalM AvaHabHi'T An I
tvailable from the National Techni:al T' e Commission hrs determined Regulatory Research U.S. Nuclear h
Information Servios,5285 Port Royal under the National Envimamental Regulatory Comtalasian, Washington, Road, Springfield, VA 22161. A copy is elso avas1=h6 for inspection and Policy Act of 1969, as amended, and the DC 20555. telephone (301) 415-6010, copyic6 or a fee in the NRC Public Commission's regulations la Subpart A XILPaperworkReduction Act f
Dacumane Room 2120 L Street, NW, of10 CFRPart 51, that this proposed Statement (lower Level), W on. DC.
regulation,if adopted, would not be a Copir4 ofissued guides mm)ar Federal action significantly his y,-j : ' regulation a:nends may be -# - ' frasm the Goven. ment affecting the quality of the human information coHection r ' -
- that PrMOf5ee (GPO) at the current GPO er.vircamant and therefore an are subject to the Papenduk Reduction price. Infa===riaa on cuneet CPO enviran=eatal impact statement is not Act of 1980 (44 U.S.C. 3501 et seq.).
pdcas may be obtained by e~ia=
required.
This proposed regularia= bas been the N " ' - of rucumanea tJ.S..
'the mvisions associated with the submitted to the OfEco of unnag==lcf aan
~
and Budget for review and approva Covunument Printing OfBon, Mall Stop mector siting criteria la to CFR part WO SSOP, Washington, DC 20402-0328.
and the r.aar=+i-of the plart design the
^
^ frosa to CFR pa t 100 to is no pu'bWseportingburden lesund guidas may alsobe purchamad r= r- _
from the National T=chale=1 Information 10 CFR Past 50 havebeen evaluated related to the =a===a==ic enting criteria.
Service on a standing order hemis.
againstthe cunent ts. % e Public re burden for the Detaus on this service n.sy be obtained Commission has udad that collection of related to the i
by wri Nf1S,5828 Port Rcyal Road, relocating the mquirement for a dose seismicandearthquake 7 :.' g calculatlan to Part 50 and more critada is==eimanad to average 800,000 S
VA 22161.79-300 SECY 90-016, SECY spedlic she criteria to part 100 not hours per response, including the time 93-087,and WASH-1400 ass avat1=hla decrease the pr *actia= of the public formeiewlaginstr=*tana searching forinspection and for a fee at healthand safety over the runent existing data sources, gathering and the amm1== ion's Document regulatta== %e amendments maintaining the data needed,and,
r Room,2120 L Strust NW. (Lower do not affect plant completing and reviewing the collection level). Washington,DC.
efnuents and have no ofinfonnation.
enviraamantalimpact.
Send r=====*= regarding this burden pg.,_,ge_m g, he addition of 5100.23 to 10 CPR esti;nate or any other asped of this Elecamete Format part 100, and the addition of appendix collection of infonnetion, including
%e comment process willbe S to to QR part 50,will not diange the q '- for seducing this burden,to improved if each ramment is identified radialagical enviran==ntalin the Information and Records with the document title, section offsite.Onsite occu tion Management Branch (T-6 F33), U.S.
heading,and peregraph number exposure=== arias withinspedian and Nuclear Regulatory Cam =lemlon, main===ana will not diange Dese Washington, DC 20555; and to the Desk' addressed. Commenters era encouraged e
to submit, in addition to the original activities are principally associated with Officer OfEco ofInformation and paper copy, a copy of the letter in base line inspections of structures, Regulatory Affairs,NEOB-10202, l
l
522GG Fed:r:1 Register / Vol. 59 No.199 / Monday, October 17, 1994 / Proposed Rules (3150-4011 and 3150-4093), Office of List c.f Subjects U.Sc 2234). Appendix F riso issued und;r Managarent and Budget, Washington' D CFR Port 50
- 2. Section 50.2 is amended by adding DC 20503.
Antitrust, Classified information*
in alphabetical order the definitions for 1
[
XIII. Regulatory Analysis Criminal penalty, Fire protection-Committed dose equivalent, Committed Intergovernmental relations, Nuclear effective dose equivalent, Deep-dose U
The Commission has prepared a draft p wer plants and reactors, Radiation equivalent, Exclusion area, Low regulatory analysis on this proposed pr tection, Reactor sitmg critena, population zone, Safety-related lI regulation. The analysis examines the Reporting and recordkeepmg structures, systems, and components costs and benefits of the alternativos rnquirements.
and Total effective dose equivalent to considemd by the Commission. The read as follows:
draft analysis is available for inspection 10 CFIT Port 52 in the NRC Public Ducument Room, Administrative practice and 6 50.2 Definitions.
p 2120 L Street NW. (Lower level),
procedure, Antitrust, back6tting, l
Washington, DC Single copies of the Combined license, Early site permit, Committed dose equivalent means the 4
analysis are avallable from Mr. Leonard Emergency planning Fees, inspection-dose equivalent to organs or tissues of Soffer, Office of Nuclear Regulatory Limited work authorization, Nuclear reference that will be received from an i
Research, U.S. Nuclear Regulatory power plants and mactors, Probabilistic intake of radioactive material by an Commission, Washington, DC 20555, risk e.ssessment, Prototype, Reactor individual during the 50-year period tele one (301) 415-6574, or Dr.
siting criteria, Redress of site, Reportin8 following the intake.
An w ). Murphy, Office of Nuclear and recordkeeping requirements, Comnutted effecuve dose equivalent Regulatory Rosearch, U.S. Nuclear Standard design, Standard design is the sum of the products of the Regulatory Commission, Washington, certification.
weighting factors applicable to each of DC 20555, telephone (301) 415-6010.
the body organs or tissues that are f
10 CFR Part 100 p
The Commission requests pubhc irradiated and the committed dose J
comment on the draft regulatory Nuclear power plants and reactors, equivalent to these organs or tissues.
4 analysis. Comments on the draft Reactor siting critena, j
analysis may be submitted to the NRC For the reasons set out in the Deep-dose equivalent, which applies f
preamble and under the authority of the Atomic Energy Act of 1954, as amended, to external whole-body exposure,
{
as indicated under the ADDRESSES dose equivalent at a tissue depth of 1 cm heading.
the Energy Reorganization Act of 1974, XIV Regulatory Flexibility Certificat,on as amended, and 5 U.S.C. 553, the NRC
,"gf'"2) f In accordance with the Regulatory is pmposing to adopt the following Exclusion area means that area amendments to 10 CFR puts 50,52 and surrounding the reactor, in which the Flexibility Act of 1980 (5 U.S.C 605(b)),
- 100, the Commission certifies that this reactor licensee has the authority to determine all activities including PmPosed regulation will not,if PART 50-DOMESTIC LICENGING OF exclusion or removal of personnel and promulgated, have a significant PRODUCTION AND UTILIZATION PmPerty from the area.%Is area may be economic impact on a substantial FACILITIES number of small entities. %is proposed traversed by a highway, railroad, or regulation affects only the licensing and 1.The authority citation for part 50 waterway, provided theye are not so operation of nuclear power plants.
continues to mad as follows:
close to the facility as to interfere with J
Nuclear power plant site applicants do Authority: Secs. t02,103, t04, t05,161, normal operations of the facility and not fall within the definition of small 182, tea, too, tes, se Stat. 936, car, ess, provided appropriate and effective busi-ises as defined in Section 3 of the 94s,953,954,955, eso, as amended, sec.
arrangements are made to control traffic Small Business Act (15 U.S.C 632), the 234, as Stat.1244, as amended (42 U.S.C-on the highway, ralhoad, or waterway.
Small Business Size E*.andards of the 2132,2133,2 34,2135,2201,2232,2233, in case of emergency, to protect the 2236, 2230,2282); secs. 201, as amended, public health and safety. Residence l I Small Business Administrator (13 CFR aa 42 u m
part 121), or the Commission's Size
$2 within the exclusion area aan nonn@
g g84 6
Standards (56 FR 56671; November 6*
Selon 50.7 also issued unda Pub. L gp - be prohibited. In any event, residents 1991)-
60s, sec.10,92 Stat. 2951 as amended by shall be subject to ready removal in case Pub. L 102-486, sec. 2002,106 Stat. 3123, of necesity. Activities unrelated to XV* Backfit Analysis (42 US.C 5851). Section 50.10 also issued operation of the reactor may be
%e NRC has determined tha',the under secs.101,185.66 Stat. 936,955 as permitted in an exclusion area under t
amended (42 m 2131,2235), sec.102-appro riate limitations, provided that backfit rule, to CFR 50.109, does not Pub. L 91-190,83 Stat. 653 (42 USC 4332). nosi ificant harnrds to the public I to t regulation and d$
herekore,his pro analysis is not Ued un heal and safety will result.
a ba
- 108, Sut. e required for this proposed regulation amended (42 USn 213a). Sections 50.23, because these amenaments do not 50.35,50.55, and 50.56 also issued under sec.
IN Population zone means the area involve any provisions that would tas,64 Stat. 955 (42 USC 2235). Sections immediately surrounding the exclusion impose backfits as defined in 10 CFR 50.33a, so.55a and Appendix Q aleo issued area which contains residents, the total under sec.102, Pub. L 91-190,83 Sta'. 853 number and density of which are such
'i 50.109(a)(1). %e proposad regulation (42 U.Sc 4332). Sections 50.34 and 50.54 that there is a reasonable probability would apply only to applicants for als issued under sec. 204,88 Stat.1245 (42 that appropriate protective measures future nuclear power tant construction
- t. '
e uld be taken in their behalf in the permits, preliminary esign approval, U(
ni ed n b.
e event of a serio.ts accident.These final design approval, manufacturing 2073 (42 USA 2239). Section so.7s also licenses, early site reviews, operating 1seued under sec.122,68 Stat. 939 (42 U.Sn guides do not specify a permissible licenses, and combined operating '
2152) Sections 50.80-50.81 also issued population density or total population licenses.
under sec.184,68 Stat. 954, as amended (42 within this zone because the situation 1
l
{d Fed r:1 F-T ir / Vol. 59, No.199 / Monday, October 17, 1994 / Proposed Rules 52267 may vary from case to case. Whether a permit pursuant to this part or a design release
- from ths core into the speci6c number of people can, for artification or combined license matainment --ning that the facility j
example, be evacuated from a spectiac pursuant to pa t 52 of tha chapter,shall 1 operated at the ulthnata power level y
timsly tris will depend on many section.
perform an evaluation and analysis of
%p cree, or instructed to take shelter, on a
. comply with paragraph (a)(1)(i) of this contemplated.W apphcant shall factors such as location, number and
. (i) A description and safety the postulated fission product release, p
assessment of the site on which the using the expected demonstrable B
sir.e of highways, scope and extent of facility is to be located, with appropriate containment leak rate and any fission g
a;dvcnce planning, and actual attention to features affecting facility product cleanup systems intended to p
s distribuuon of residents within the area.
design. Special attention should be mitigate the consequences of the directed to the site evaluation factors accidents, together with applicable site identified in part 100 of this chapter.
characteristics, including site com tr as s ru The assessment umst contam au meteorology, to evaluate the ou ite i
r s
systems, and components thst are relled analysis and evaluauou of the major radiological consequences. Site on to remain functional during and structures, systems and components of characteristics must comply with part folio"I"8 esign basis (P08tu!ated) the facility which bear signifimatly on 100 of this chapter. b evaluation must I
d swnts to assure;.
the acceptability of the site under the determine that:
(1) The lategnty of the reactor coolant site enluation factors identified in part
(;) An individual located at any point I
Pressure bandary' o shutdown the 100 of this chapter, assuming that the on the boundary of the exclusion area (2)ne capability t facility will be operated at the ultimate for any 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period following the
-l reactor and maintain it in a safe power level which is contemplated by onset of the ulated fission prA.t i
shutdown condition,and the applicant. With respect to operation rab+<e, wo et remive a radiation (3)ne capability to prevent or at the projected initial power le vel, th?
oose in excess of 25 ' rem total effective mitigate the consequences cf accidents licant is required to submi' dose equivalent (TEDE),
ap[ormationhrescribed in p iragraphs which could resuh in potential offsite g,
(2) An individual located at any point exposures comparable to the applicable (aX.2) hou MW of % mcuan, as mhe hdary of blow guidehne expmums ad fath,in 1 m & informadan requhed by % po um@ hpmed to &
7 S 50.34(a)(1) or $ 100.11 of this chapter.
p graph,in support of the application
-oncun cloud resulting from the for a construction permit, or a design oostulated fission product release I; '
Total effective doar equivalent (TEDE) 7h '-- P " ia radiation dose in~riod ofits passage) ap(proval.ii) A description and safety woul[not receiv means the sum of the deep dose equivalent (for external exposures) and assessment of the site and a safety excess of 25 som total effective dose ths committed effective dose equivalent assessment of the facility, it is expected "uivalent (TEDE)
(for internal exposures).
that reactors will reflect throu8 their (E) With respect to operation at the h
design, construction and operation an pro}ected inidal powwlevel,the e
+
a a
e
- 3. In 5 50.8, paragraph (b)is revised to extremely low probability for accidents applicant is required to submit read as follows:
that could result in the relenae of informadan bed in paragraphs significant quantitia of radioactive (a)(2)
(a)(6)of thissection,as 5sa.s In k nesoncameomen fission producss.b following power well as b aformation required by this
'espeemen: cess appmet.
reactor design characteristics and ph,in support of the a limtlen proposed operadon willbe taken into construction permit, or a7esign (b)h approved information consideration by the Commission:-
,PP,,ng, mllection ;
5= -
^ containedin (A) Intended use of the reactor this part appearin $$ 50.30,50.33, including the pro mavimum p
g 50.33a, 50.34, 50.54a, 50.35, 50.36, wer level and e nature and OF M MA1, MI.4, dadanary power 50.36a, 50.48, 50.49, 50.54, 50.55, ventory ofcontained radioactive reactor appliants who apply for a g
' 50.554,50.59,50.60,50.61,50.63,50.64, ' materials; constmction pwmit pursuant to this 4
50.65, 50.71, 50.72, 50.80, 50 A1, 50.90, (B)b exteat to which y
50.91, and A- - -* A,B, E,G, H'I*
acce ed ering =8=
nds am d}
m "? * -*.*-
87cd.xt.nt2'w"2*s'.~e'n*a P4" "h=" 2r"',e"'
c
- 4. In i 50.34, foo*. notes 6,7, and 8 are inewpmetesuni us,umasualm Mtem d
en a
mais easden ge nuy 4 as Emaenata= 4,9 and 10 be====*8 8 *=ek la enhetueW mahdown d y
signi8 cant bearingon the ty or alease d the can wie s,ehsequent solemme b,eo the, g,,i,,
[g and parapsph(aM1)is avvised and masequenne d a d,
_m, w m
(aM12),(bM10), and (bM11)
- CII" Id"C" F
, -- didInd to read as follows~
(D)b safety features that are to1,6
- 4 mm.Jy deus et as na benbeen siened H
are se _
' is she ence sn.e suethme 4
gSa.54 conessesogappuommons, technical. engineered into the fadlity and those socidast er amersemey Mrman -werken r
insermeson, harriersthat mustbe breached as a
,"",, g,,ia**Q"%
g result of an accident before a misess of (t) e e a
radioactive material to the enviranmaar a,,Wieden supsima semiu (me NBS Hasdtesek (1) Stationary power reactor applicants for a ranstruction permit can occur.Specielattention must be se deind bane s, tesek Howmr. tu see is met do directed to plant des features namedadis the hisnumbermessistessem LurnLt to thisJ"'h*.,2 u.si'"
- 2*eJ:"
i
.e,.t7eraf 3
-~' '
in-dediomiu de ruuaiasiai s
1u on a ee pursuant to Part 52 of this chapter who casequencesof accidents.In ha been est sere to ele
-ei== en a seseeance cpply on or aAer (EFFECITVE DATE OF Perfaming &ls a======ent, an alu, wwe een he med in she miamina et plant
- PP cant shall assume a fission product p y we6inspen te peessioned neceae -
il
'niE MNAL RULEl, shallcomply with paragraph (a)(1Xii) of this section. All pie moemmon w h,w nik as puhuc supesen m -
other applicants for a construction redisuaa. in the seent et such accidmets.
,, ~ -
j-52268 Federtl Regist:r / Vol. 59, No.199 / Monday,- October 17, 1994 / Proposed Rules 4
part, or a design certification or -
FINAL RULElitha o r tinglicense (2) W ctpability to shut down the reactor j
combined license pursuant to part 52 of EPplicent shril comply with ths earthqu:Le end meint:in it in a safs shutdown condliton.
- this chapter, as partial conformance to engineering criteria in Section VI of appendix or General Design Cnterion 2 of ap ndix A to to CFR part 100.
(3) The capability to prevent or mitigate the
""9"""
'I ' " *""
A to this part, shall comply with e
- 1. Introduction n Potential offsite exposures comparable to eequde engineering criteria in Each applicant for a construction permit, the guideline exposures of 5 50.34(aX1Xil).
ap endix S of this part-operating license, design certification, or surface deformation is distortion of I
combined license is required by gologic strate at or near the smund surface (10) On or after (EFFECTIVE DATE 5 50.34(aM12), (bX10), and General Design try the pmcesses of folding or faulting as a OF THE FINAL RULEl stationary power Criterion 2 of appendix A to this part to.
result of various earth forms. Tectonic
< reactor applicants who apply for an design nuclear power plant structures, surfaw deformation is associated with i
operating license pursuant to this part, systems, and components important to safety carthquake pmcesses.
or a design certification or combined to withstand the effects of natural IV. Application to Engineering Dolou h
P enomena, such as earthquakes, without The following are license pursuant to part 52 of this chapter as partial conformance to I 68 of C8Pabihty to pedorm their selety and geologic design bursuaut to the wismic is requirements of General Design Criterion 2 of appendix functi ns. Also, as specified in 5 50.54(ff),
5100.23 of this chapter:.
l4 A to this past, shall comply with the nuclear Powr plants that heve implemented (a) Vibratory Ground Motion.
the earthquake engineering criteria descibed (1) Safe Shu+down Earthquake Ground earthquake engineenng criteria of herein must shut down if the criteria in Motion.& Safe Shutdown Earthquake appendlx S to Ws part. However,if the paragraph fv[aX3) of this appendix are.
Ground Motion must be characterized by
!l construction permit was issued prior to exceeded.
fm. field smund motion response s :tre et l EFFECTIVE DA'E OF THE FINAL These criteria implement General Design the free ground surface. In view of KULEl, the stationary power reactor Criterion 2 insofar as it requires structures, limited data evailable on vibratory ground applicant shall comply with the systems, and components important to safety motions of strong earthquakes. It usually will earthquake engineering criteria in to withstand the effects of earthquakes.
be oppmpriate that the design response spectm bomaaM sp ne hodsontal l '
Section VI of appendix A to part 100 of g Sc,Pe oosnponent of the Safe Shutdown Earthquake
. this chapter' fter (EFFECTIVE DA*EThe evaluations described in this appendix Ground Motion in the frwfield et the (11) On or a are within the scope ofinvestigations foundation level of the structures must be an OF THE FINAL RULEl, stationary power permitted by 5 soao(cK1). '
eppropdate roeponse spectrum with a peak reactor apph, cants who apply for an ground acceleration of at least 0.1g.
operating license pursuant to this Part, IH. Definitions
& nuclear power plant must be designed J
or a combined limnse pursuant to part As used in these criteria:
so that,if the Safe Shutdown Earthquake j
52 of this chapter, shall provide a Combinedlicense means a combined Ground Motion occurs, certain structums, description and safety assessment of the mastruction permit and operating license systems, and components will remain site and of the facility as in with conditions for a nuclear power facility functional and within applicable streu, i
$ 50.34(a)(t)(ii) of this part.
issued pursuant to subpart C of part 52 of this strain, and defonnation limits. In addition to chapter.
seismic loads, appilable s, s.u.t normal Design Gertification means a t'a== lesion OPereting. func*in==1 and accident-induced
- 5. In $ 50.54, paragraph (if) is added approval,inued pursuant to subpart B of loads must be taken into account la the 1
to read as follows:
part 52 of this chapter, of a standard design design of these safetyaleted structums.
for a nuclear power facility. A design so systems,and ea paaaa*=.no design of the
$M ConmonaoHoenees.
approved may be referred to es a " certified nuclear power plant must also take into standard design.a acemt the possible e5ects of the Safe.
(ff) Forlicensees of nuclear power
& Cpetofisig Basis Y ' - Ground Shutdown F_ ',
Ground Motion en the plants that have implemented the Motion (OBElle the vibre ground notion I'[""
carthquake engirsering critesla in
.or whica those features of nuclear power muhment. ' c'--= u d n= w a ng a und the henkh safety Quired in Ib w pen 100 of eis I
IV(a)(3) of appendix S. Prior to meuming T
equimd safety functions of structums, operations, the lie =n=== ahall g,,,g,,,,,.t=aad with t shutdown and synees,and nun besamrod
)
y demonstrate to the t'a==taaion that no during and ener time vihre motion
- j inspectbo unten spec ly uneeted by ee functional damage has occurred to those applicant es a design input. -
wOsafe e
u 2,es,or.s.,em,u.ose,ioto,6e
,,,,,'8., _._ _er a en-foam,es y fo, ontinued operation without undue risk to the
==vi=um neponsee (soneleration, velocity, health and safety-of the public and the or displacement) ofidealised "-j- ?
N eveliinlom amort uke im o ecoou s m a.
i
. limnainy basis is maineannant of-freedom escillators as a function ofik-muucture imoremaan anece end se==p=aani durstlos of motion. It is p===t==Ela
- 6. Appendix S to Part 50 is added to natural",
" of the==can=a==e far a '
w dalga ser arela la esassi of yleid ~
~'
given damping value.m spectam strain in some of these safety selsted pad as follows:
is oniculated fora speci8ed motion mrucaues, systems,and -
-- during Appendix S to Part M % ;L sake' input et the oscilletors' supports.
Engineering Criteria for Nuclear Power sofsshutdownRC " Groemd - se Sale Shadown Esthquain Gmund.
i Motion and under the postulated concurrent Plants Motion (SSE) is the vibratory ground motion loads provided the necessary safety for which aestain structures, systems, and functions an malatained.
GomeralInformaties componente must be designed to nomain (2) Operating Beste Earthquaka Ground
%1s appendix applies to eppliants for a fuaMa==I Motion.
design certiflation or c*nhl==nt lloonee The structases. systems, and cornponents '
(i) The Operettag Basis Earthquake Oround pursuant to part 52 of this chapter or a regvited to withstand the offsces of the Sofe Motion must be chereceerimod by se -
corutruction pennit or operating license Shutdown Earthquake GroundMotion er.
spectra.& value of the Operettag pursuant to Part 50 of this chapter on or eher surface deformation are those==<====y to Earthquaka Ground Motice unist be est to IEFFECT1VE DATEOFTHE FINAL RULE l, assure: '
one of the following choices.
However. if the construction permit was (1) h integrity of the reactor coolant (A) One-third or nees of the Safa Shutdown lesued prior to IEPFBCTIVE DATE OF THE pressure boundary, Earthquake Ground Motion design susponse
Federal Regist:r / Vol.' 59 No.'199 / Monday, October 17, 1994 / Proposed Rule's 52209 k
spectra. The requirements associated with PART 52-EARLY SITE PERMITS';
oper-tion. This base reflects that the
(
this Operating Basis Earthquake Ground STANDARD DESIGN primary factors that determine public L
Malon in paraW (a)(2)(1)(n)(1) can be CERTIFICATIONS; AND COMBINED health and safety are the reactor design, h
o satisfied without the applicant performing LICENSES FOR NUCLEAR POWER construction and operation.
l cxplicit response or design anal see,or PLANTS (c) Siting factors and criteria are t
(B) A value greater than one. 1:d of the mportant in assuring that radiological 4
Safe Shutdown Earthquake Ground Motion
- 7. The authority citation for part 52 doses from normal operation and O
rn b fo d emon t e t th postulated act.idents will be acceptably h
cmhes to mad as Mows:
requirements assoc.iated with this Operating Authority: Secs. 103,104,161,182,183.
Iow, that natural phenomena and
!j BIsis Earthquake Ground Motion in 186.189. 68 Stat. 936,948,953,954. 9$5.
potential man-made hazards will be paragraph (s)(2)(1)(DJ(!) are satisfied. The 950, as amended, sec. 234,83 Stat.1244, as appropriately accounted for in the e, t design must take into acxxnmt soil-structure amended (42 U.S C. 2133,2201,2232,2233.
design of the plant, and that the site interaction effects and the duratiou uf MM, NE MU, sus. M. m,2E 68 characteristics are amenable to the vibrxto'7 Smimd motion.
Stat.1242.1744,1746, as amendad (47 U.S C (I) When subjected to the effect. of the 5841,5842,5846).
development of adequate emergency g
g Operating Basis Earthquake Gmund Motion
- 8. In S 52.17, the introductory text of security measures to protect the plant.
l in combination with normal operating loads' paragraph (a)(1) and paragraph (e)(1)(vi)
(d)' Itis approach inco orates the i
sary{eDMof Po are revised to read as follows:
appropriate standards an criteria for e n ci powe p t s
continued operation without undue risk to
$ 52.17 contents of appitcations.
appmval of stationary power and testing ths bedth and safety of the public must reactor sites. The Commission intends rerrein functional and within applicable
'*##I stress strain, and deformation limits.
th i formation "9ul Y
33 (a) depth approach with regard to reactor j
(3) Required Plant Shutdown. af vibratory through (d), the information required by ground motion exceeding that of the S 50.34 (a)(12) and (b)(10), and to the siting to ensure public safety. Siting l
,,,, from densely populated centers Operating Basis Earthquake Gmund Motion extent approval of emergency plans is has n and will continue to be an h
or if significant plant damage oaurs, the socght under paragraph (b)(2)(ii) of this important factor in evaluating l ~.
licensee must shut down the nuclear power section, the information requirvi by plant. If systems, structures, or components S 50.33 (g) and (j), and S 50.34 (b)(6)(v).
ap g ca ns ggr site op g
necessary for the safe shutdown of the The application must also contain a fogg *'.
,~
nuclear power plant are not available after description and safety assessment of the h'
ths cccurrence of the OBE the licene must site on which the facility is to be
$ 100.2 Scope.
[m
, safeIhutdown I cated.*Re assessment must contain The siting requirements contained in la f he t of ths nucfear power plant. Prior to resuming an analysis and evaluation of the major this part apply to applications for site operations, the licensee must demonstrate to structures, systems, and components of approval for the purpose of constructing
, A; <
the Commission that no functional damage the facility that bear significantly on the and operating stationary power and K
has occurred to those features necessary for acceptabilMy of the site under the testing reactors pursuant to the fi*
continued operation without undue risk to radiological consequence evaluation provisions of parts 50 or 52 of this the bealth and safetyof the public.
factors identified in S 50.34(a)(1) of this. chapter.
(4) Required Seismic Instrumentation.
chapter. Site characteristics must
- 13. Section 100.3 is revised.to read as Suitable instrumentation must be provided comply with part 100 of this chapter. In follows:
to that the seismic response of nuclear power addition,the a plication should
)
l P ant features important to safety can be describe the fo kwb.
$100.3 Definitions.
1 8-evaluated promptly after en earthquake.
As used 6 this pam g't (b) Surface Deformation. The potential for surface deformation must be taken into (vi) The seismic, meteorological, Combinedlicense means a combined n,
account in the design of the nuclear power hydrologic, and geologic characteristics construction permit and operating
+
P ant by providing reasonable assurance that of the proposed site; license with conditions for a nuclear l
in the ennt of deforrostion,certain Power facility issued pursuant to i.
structures, systems, and components will subpart'C of part 52 of this chapter.
PART 100--REACTOR SITE CRITERIA Early site permit means a Commission
[
remain functional. In addition to sudac*
defonnation induced loads, the design of approval, issued pursuant to subpart A 4
i safety features must take into amount seismic
- 9. and 10.The authority citation for of part 52 of this chapter, for a site or loeds, including aftershocks, and ap 11 cable Part 100 continues to read as follows:
sites for one or more nuclear power concurrent functional and accident-nduced loads.The design lans for sudace Authority: Secs.103,104,161,182,68 g,c[gjges.
deformation must based on its postulated Stat. 936,937,948,953, as amended (42 Exclusion area means that area i
occurrence in any direction and azimuth and U.S4 2133,2134,2201,2232); sec. 201, as surrounding the reactor, in which the
,4 under any of the nuclear power plant, amended. 202,88 Stat.1242, as a:nended, reactor licensee has the authority to u:less evi[nos indicates this assumption is 6
1244 (42 U.Sc 5s41, s842).
determine all activities including not cppropriate, and inust taka into account
- 11. Section 100.1 is revised to read as exclusion or removal of personnel and
.f the estimated rate at which the surface follows:
property from the area. This area may be q
defoemation may ocar.
traversed by a bl hway, railroad, or i
6 (c) Seismically Induced Floods and Water
$ 100.1 Purpose, waterwey, provided these are not so i
W:ws csd Other Design Cooditions-(a)'Ibe purposc of this past is to close to the facility as to interfere with Seismically laduced Doods and water waves frorn either locany or distantly generated establish approval requirements for normal operations of the fadlity and
-k proposed sites for stationary power and provided appropriate and effective b in testing reactors sub}ect to part 50 or part arrangements are made to control traffic A
t 1
o chapter must be taken into account in the 52 of this chapter.
on the hi way, railroad, or waterway,
{
design of the nuclear power plant so as to (b) There exists a substantial base of in case o emergencysto pmtect the y
prevent undue risk to the bealth and safety knowledge regarding power reactor public health and safety. Residence of the public, siting, design, construction and within the exclusion area shall normally
52270 Federd Regist:r / Vol. 59, No.199 / Mondty, October 17, 1994 / Proposed Rules
.t lll 5
ha prohibited. In any event, residents communicttions submitted pursuant to determining tha acceptability cf a sits shall bnuhjact to ready removal in case 10 CFR part 100 should be addressed to for a power or testing roador:
of nomsshy. Activities unrelated to the U.S. Nuclear Regulatory la) Characteristics of reactor design Commission. ATTN: Document Control and operation including-operation of the reactor may be Desk, Washington, DC 20555, and including the proposed maximum (1 tended use of the reactor perraitted in an exclusion area under copies sent to the appropriate Regional power level and the nature and appmpriate limitations, provided that no significant hazards to the public Office and Resident inspector.
bealth and safety will result.
Communications and reports may be inventory of contained radioactive materials; j
Low populaiion zone means the area delivered in person at the Commission's (2)The extent to which generally immediately surrounding the exclusion offices at 2120 L Street, NW.,
accepted engineering standards are area which contains residents, the total Washington, DC, or at i1555 Rockville epplied to the design of the reactor:
number and density of which era such Pile Rockville, Maryland.
- 13) The extent to which the reactor C
'* tion 100.8 k revised to read as that there is a reasonable probability incorporates uruque or unusual ieutures that appropriate protective measures fota -
having a significant bearingon the muld be takenin their behalfin the 5 m intmnatim collectim probability or consequences of t
event of a serious accident. Theso requirements: OMB approval.
accidental release of radioactive guides do not specify a permissible (a)The Nuclear Regulatory materials; population density or total population Commission has submitted the (4)The safety features that are to be within this zone because the si:ustion information collection requirements engineered into the facility and those may vary frorn case to case. Whether a contained in this part to the Office of barriers that must be breached as a specific number of people can, for Management and Budget (OMB) for result of an accident before a release of Ij example, be evacuated from a specific approval as required by the Paperwork radioactive material to the enviromnent area, or instructed to take shelter, on a Reduction Act of1980 (44 U.S.C. 3501 can occur.
timely basis will depend on many (b) Population density and use i
factors such as location, number and et seq.). OMB has appeoved the charaderistics of the site environs, information collectiou nts size of highways, scope and extent of mutained in this part un er control including the exclusion area,loy population zone, and the population I
advance planning,and actual number 3150-0093.
I distribution of residents within the area.
(b) The approved information (c) Physicalcharacteristics of the site, center distar,ce.
h'.
Population center distonce means the couection requirements contained in.
including seismology, meteorology, distance hom the reador to the nearest this part appear in $ 100.23 and geology, and hydrology, boundary of a densely populated center Appendix A.
(1)A ndix A to Part 100. " Seismic containing more than about 25.000
- 16. A heading for Subpart A and Geo c Siting Criteria for Nuclear residents.
(consisting of 55100.10 and 100.1i)is Power Plants" describes the nature of Power reactor means a nuclear teactor added directly before $ 100.10 and of a type described in $$ 50.21(b) or 66100.10 and 100.11 are revised to read investigations requhed to obtain the 50.22 of this chapter designed to Eaologic and seismic data necessary to as follows:
produce electricalor heat energy.
determine site suitability and to provide A flesponse spectrum is a plot of the Subpart A--Evaluation Factors for nasonable assurance that a nuclear maximum responses (acceleration.
Stationary Power Reactor Olte power plant can be conc *ructed and velocity, or displamment) of idealized Applications Before (EFFECTIVE DATE operated at a site without single-degree-of-freedom oscillators as a OF THE FINAL RULE) and forTesting undue risk to th health and safety of function of the natural cies of the public. it describes procedures for Reactor
- the oedllators for a given ping determining the quantitative vibratory is 3 c, gr und motion d basis at a site due veno.He response sybratory calculated for a ned vi 100.10 Factors to be considered h to earthquakes and motion taput at oscillators
- evaluating sites, information needed to statarmW 100.1i Determination of exclusion area, low whetherand to what extent a nuclear supports.
The Sofe Shutdown Entthquake population zone, and population center Power plant needbe designed to Ground Modon is the vibratory ground dimance.
withstand the effects of surface faulting.
c80'8 to l** *N *ba (2) Meteorologimiconditions at the motion for which certain structures, systems,and components mustbe MM**#**-
site and in the surrounding area should designed pursuantto Appendix S to
-Factors considered in the evaluation be considered.
50 of this chapter to remain isitesincludethose relatabothto (3)Geologicaland hydrological cuond the proposed reacioe design sad the characteristics of the proposed site may Swface deformotion is distortion of characterisucs peculiar to the site. It is have a on the masequences of an esca of ve matarla! from geologic strata at or near the d
- xPected that reactors will reflect through their design, construction and the ty.Spedal precautions should surfaceby the processes of to or faulting as a result of various Peration an extreme low probability be planned if a reactor is to be located forces. Tectonic surfaa deformation is for accidents that co resultin release at a site where a significant quantity of j
a sociated with earthquake processes, of significant quantities 6f sudioactive redioective effloent might acx:identally Testing reactor means a tesung focflity fission products, la addition, the site flow into nearby streams or rivers or as definedin S 50.2 of this chapter.
location and the engineeked, features might find ready access to underground l
- 14. Section 100.4 is added to read as included as safeguards signinnf.the water tables.
(d) Where unfavorable physical i
follows:
hazardous consegeences of an accident, characteristics of the site exist, the should one owur, shouldinsure alow 5t00.4 communications.
Except where otherwise specified in risk of public expcx,ure.In particular, proposed site may neverthelessbe this part, all correspondence, reports, the Commission will take the following found to be acceptable if the design of factors into consideration in the facility includes approprieto and l
spplicatlans, and other written 4
Fed:re.1 It=gder / Vol. 59, No.199 / Monday, October 17, 1994 / Proposed Rules 52271
.s b
- 17. through 19. Subpart B ($$ 100.20-adequate compensating engineering upon musideration of population 100.23)is added to read as follows:
y dist ribution. Political boundaries are not
uld determine the envelopes of b plan overlay of the f:1 owing.
areas so calculated shall then be taken for a stationary power reactor:
(1) An exclusion area of such size that as their respecdve boundaries.
(a) Population density and use an individwl located at any point on its (2) If the reactors are interconnected characteristics of the site environs, boundary b two hours immediately to the extent that an acx:ident in one Muding the exclusion area,the following onset of the postulated fission reactor could affect the safety of population distribution, and site-related characteristics must be evaluated to l
product release would not receive a operation of any other, the sae of the exclusion area, low populadon zone and determine whether individual as well as total radiation dose to the whole body 12 Excess of 25 rem 8 or a total radiation population anter distance shallbe societal risk of potential plant acciduts does in excess of 300 rem to the thyroid 8'ased upon the assumption that all is low, and that site-related i
imm iodine exposum.
interconnected reactors emit their characteristics would not prevent the I'
(2) A low population zone of such Postulated fission product releases development of a plan to carry out ri.* P ; " "" actions for members size that an individual located at any simultaneously. This requirement m.y of the public in the event of emergency.
point on its ater boundary who is be reduced in relation to the degree of exposed to the radioactive cloud coupling between reactors, the related hazards (e.g., airports, dams, F
(b)The nature and proximity of man-
[
resulting from the postulated fission probability of concomitant accidents product release (dunng the entire period and the probability that an individual transportation toutes, military and cf its passage) would not receive a total would not be exposed to the radiation chemical facilities) must be evaluated to radiation dose to the whole bodyin excess of 25 rem or a total radiation efrects from simultaneous releases.The establish site parameters for use in does in excess of 300 fem to the thyroid applicant would be expected to justify determining whether a plant design can to the satisfaction of the Commission accommodate commonly ca:urnng (3) A population center distance of at the basis for such a reduction in the hazards, and whether tim risk of other from iodine exposure.
i hazards is very low.
least one and one" third times the source term.
diananna from the reador to the oder (3)ne applicant is expected to show (c) Physical characteristics of the site, Sun of the low population zone.In that the simultaneous operation of including seismoloin, meteo: ology, 4PI this guide,the boundary of the multiple reactors at a site will not result geology,and hydmfogy.
tion center shallbe determined in total radioactive e81uent releascs (t) $ 100.23." Geologic and seismic beyond the allowablelimits of siting fadoes," of this part describes the j,g,6m g mism _---din applicable regulations.
criteria and natum ofinvestigations sm Note: For further guidano, la developlag required to obtain the geologic and
,p seismic data n====ary to determine the 1
Lemisi d h.m.ser pwp.r.aw 4; iy.i.,
the exclusion ares,ihe now population mone,
-d -a ' w e thea =.uld reeuk in p.s.mtist and the population center d'=*=a~, mimace suitability of the proposed site and the
.t p.mai.
5 p
i issondetoTaawlInfonnettom "-t laat design bases.
r h md ass em dadgeb = nom my w--'
088 " 88 (2) Meteorologicalth of noen m Y.d mke.wn[
4844'_d'88 &"
u,on w des h.a""'I"J g umi AIO,le wind speed and
" "Ne' m k ha
!'E'.'0".lll"'t l" Lee.f#.e.*in
I-2Md?"'"""i u.
b
- os_
probab mum.JentiSed and charaderised.
[
me shu d s,. am Tach-wl Infor==*i.mrue =* 14s44 my w.rh.= which..m.sdine i.
be used se a point of for
"" mer he " -. -
- t. tia consideration af site M
- -ts (3) Factors important to by I'
ti.wh 1 ee da'd Ew""."rja. which inmy neunt from weluation'of the radionuclide transport such as sediment, and rock.chMder,istics, charactuimia ilar seector,its oonmedre.
coe uen,a, neaker m us.mermetetm se.e i tre r
nd adso,,d water velocity, and distences to
.,mid to
.a.
ri.
sunda m. i e.edd a kapiy ** **a amb.a Copies ofTechnicallaformation groun 7huc
.ced.".aM' 7amher m"i Dar nmant 14844 anny be aheafnad imm the nearest eurface body of water) must the Commimion's Public Document be obtained Iman on site measurements.
valm how h a t 1.rth in th susd Room,2120 L Street NW.(Iower Level), %e martmum probable Aood along as as wh.i h.dy lu.ad tb. 3an mm eyroid Washington,DC,or by writing the with the antial for seismically "I."*" "I"*
- hie ca.1" "g"d l* *.**d".*"" O"$' ", K'j Diredor of Nuclear Paarear Regulation, induced diarnemartin
",,*jI,,".,
U.S. Nuclear Regulatory Commission.
$100.23(d)(3) of this part must be i.
J Washington, DC 20555.
estimated using historical data.
omen o, d h,= risk or public ap so reds uon.
m..
52272 Fed:rd Register / Vol. 59, No.199 / Monday October 17, 1994 / Proposed Rules
$ 100.21 Non-seismic siting criteria.
result in the site being found surface deformation, nontectonic Applications for site approval for ecceptable.S deformation.carthquake recurrence I
commerdal power reactors shall rates, fault geometry and slip rates, site demonstrate that the proposed site
[1j Geologicandseismicsmng foundation material, and seismically (a) Every site mast have an exclusion induced floods and water waves must meets the following criteria:
This section sets forth the principal be obtained by reviewing pertinent area and a low population zone,as gelogic and seismic considerations that literature and carrying out field o'
defined in $100.3; guide the Gommission in its evaluation investigations. Ilowever, each afplicant (b) The population center distance, as of the smtability of a proposed site and shallinvestigate all geologic an seismic defined in S 100.3, must be at least one adequacy of the design bases established factors (for example, volcanic activity) and one-third times the distance from m consideration of the geologic and that may affect the design and opeiation the reactor to thn outer hmmdary of(the seismic charactaristics of the proposed of the proposed nudcar power plant a
low population zone. in applying this site, such that, there is a reasonabl*
irrespective of whether such factor: cm
)
guide, the boundary of the population assurance that a nuclear power plant ex(nlicitly included in this section.
center shall be determined upon can be constructed and operated at the d) Geologic and seismic siting consideration of populatica Proposed site without undue risk to the factors. The geologic and seismic siting distribution. Political boundaries are not health and safety of th,e pubbc.
factors considered for design must APP cations to engmeermg design include a determination of the Safe li I
controlling in the application of this
~
guide; are contained in appendix S to part 50 Shutdown Earthquake Groand Motion l
(c) Site atmospheric dispersion of this chapter.
for the site, the potential for surface characteristics must be evaluated and (a) Appbcauility ne requirementsin tectonic and nontectonic deformations.
)
dispersion parameters established such Paragraphs (c) and (d) of tMs section the design bases for seismically induced I
that:
apply to applicants for an early site floods and water waves, and other i
l (1) Radiological effluent release limits permit or combmed license pursuant to design conditions as stated in paragraph associated with normal operation from Part 52 of this chapter, or a construction (d)(4) of this sectics.
the type of facility pro d to be Permit or operating license for a nuclear (1) Determination of the f,afe located at the site can met for any power plant pursuant to Part 50 of this Shutdown Earthquake Grormd Motion.
[
Indmduallocated offsite; and chapter on os after (EFFECTIVE DATE De Safe Shutdown Earthquake Ground j
(2) Radiological dose consequences of OF THE I".NAL RU11). Ilowever,if the Motion for the site is characterized by postulated accidents shall meet the construction permit was issued prior to both horizontal and v=tical free field criteria set forth in 6 50.34(a)(1) of this Iturun WE DATE OF'IWINAL cround motion response spectra at the i
chapter for the type of facility proposed RULE), the operating lic mi e applicant lree ground surface. no Safe Shutdown to be located at the site; shall comply with the oJsstic and Earthquake Ground Motion for the site 3
(d)The physical haracteristics of the geologic siting criteria in sppendix A t is determined considering the resutts of
~
n site, including meteorology, geology, part 100 of this chapter.
the investigations required by paragraph seismology,and hydrology must be (b) Gommencement of o>ustruction.
(c) of this medion. Uncertainties are evaluated and site parameters The investigations required in inherent in such estimates.These h
established such that potential threats paragraph (c) of this section are withia uncertainties must be addressed through from such physical characteristics will the scope of investigations permitted by an aMrepriate analysis,such as a pose no undue risk to the type of facility 550.10(c)(1) of this chapter.
p,u illstic seismic hazard analysis or proposed to be located at the site; (c) Geological, seismological,and suitable sensitivity analysee. Paragraph
[{,
(e) Potential hazards associated with engineering characteristics.The IV(a)(1) of appendix S to part 50 d 8his nearby transportclon routes, ' ? _ Ia!
- eological. seismological, and chapter defines the minimum Safe -
i and military facilities must be evaluated engineering characteristia of a site and Shutdown Earthquakt Ground Motion and site parameters established such its envimns must beinvestigated in k design that ential hazards fmm such routes sufficier t scope and detail to permit an (2) Determination of the potent 2al for r
and liries willpose no undue risk to adequate evaluation of the proposed surface todonic and nontectonic the type of facility proposed to be site, to provide sufficient information to deformations. Sufficient geol cal, i
located at the site; support e raluations pwbo,ed to arrive seismological, and geophys1 data (f) Site characteristics must bs such at estimr.tes of the Safe Shutdown must be provided to clearl establish
- i j
that adeqt. ate security plansand Earthquake Ground Motion,and to whetMr there is a potenti for surface measures can be developed; permit adequate engineering solutions deformadon.
(g) Site charuahwmustbe such to actual orpotentialgeologic and (3) Determination of design bases for that adequate plans to take protodive seismic offods at the proposed sita.The seismiallyindumd floods and water actions for members of the pvblic in the size of the region to be in. O "iand waves.%e Mme of seismially induced event of emergencycanbe developed:
the type of data pertinent to the floods and water waves that could affect (h) Reactor sites should belocated investigations must be determined a site from either locally or distantly away from very densely ulated based on the n,ture of the region generated salamic edivity must be centors. Areas oflow tion density surrounding the pro site. Data on determined.
. tre, generally, pref
. liowever,in the vibratory motion, tectonic (4) Determina+1on of siting factors for uetenntningthe a<reptabilitv of a other conditions.Sidng factors Particular site located away from a very rumpla of h haar. Inded.,but m not for other conditions that must be densely populated center but not in an Iwtedio. dis.aars the bisherpop.lettaa evaluatedi ude soiland rock i
area of low density, consideration will g'7$Dt.[" born.cr.m6aa, stability,liquefadion potential, natural i
be given to safety, environmental, ret end highw.y ea==..harter er m une and artificial slope stability, cooling 1
economic, or other factors, which may r.ga n u..ei
.ovima m s.:is,.cion water supply, and remote safety-related
$.1*d"*".d'"h s a"orimiid[d din, structure siting. Each applicant shall soin evaluate all siting fadors and potential l or imp a.th.oei.r atte. includ d to thw causes of failure, such as, the $ysical ction.
l 1
4 1
l Fed:ral Register / Vol. 59, No.199 / Monday, October 17, 1994 / Pmposed Rules 52273 j
g 4
proporties of the matmials underlying ron runTurninrORMATION Ct/ TA0r:
that the flight emw may heve ettempted f
ths site, ground disruptiva, and the Stepiaen Slotte, Aerospace En ;ineer, to override the autopilot while it was j
effects of vibratory ground motion that Standardization Branch, ANh ~-113, engaged in the COMMAND mode. If the m2y affect the design and operation of FAA, Transport AirplaneDimetorate, airplane isin pitch axis,and the the proposed nuclear power plant.
1601 Lind A-e. SW.,8btr on, autopilot is overridden for prolonged Dated at Rockville, Maryland, this tith day Washington 98055-4056; elephone periods by the flight crew via manual of October.
(206) 227-2797: fax (206) 227-1320.
input from the mntrolcolumn, and if the autopilot is subsequently 1
For the Nuclear Regulatory Commission.
SUPPt.ElsENTARY INFORMATION:
disengaged, the resultant out-of-trim 1
W C.%
Comments invited condition between the trimmable Acting Secmfaryofthe Comminim interested rsons are invued to horizontal stabilizer nnd the elevator IFR Doc. 94-25585 riled 10-1444; a A5 aml participate in e making of the could reducecontrollability of the l
proposed rule by submitting such airplane.
written data, views, or arguments as Further investigation indicates that i
they may desire. Communications shall the design of Model A300400 series l
DEPARTMENT OF TRANSPORTATION identify the Rules Docket number and airplanes does not provide for be submitted in triplicate to the address disengagement of the autopilot in, a manner that would allow for manual Federal Aviation Administration speci6ed above. All communications received on or befom the closing date I.DPut from the control column without M CFR Part 39 for comments, spedSed above, will be adversely a%cting controllability of the considered before taking action on the airplane.%e design of Model A310 1
IDocket No.N146-AD) proposed rule.De proposals mntained series airplanes is identical in this Ainsortdnese Direceves Aletius Model in this notice may be changed in light sespect to Model A300-600 series i
F ench DGACissued French
)
n are spe callyinvited on Airwrthiness Directive 94-185-165(B),
AGENCv: Federal Aviation the overall regulatory, economic, 4
Adminlahetion,IXYT.
environmental, and energy aspect"f dated August 17,1994,in order to assure the contmued airworthiness of 2
/cTioss:Notico of proposed rulemaking the proposed rule. All comments submitted will be available, both before these airplanes in France.%e Frend l
(NPRM)"
and after the closing date for comments, AD requires modification of FCC's suenaAnY:%is document proposes the in the Rules Docket for examination by having part numbers (P/N) B216ABM6, B350AAM1,B350AAM2,B350AAM3, adoption of a new airworthiness interestal persons. A report and B470ABM1(for Mcdel A310 series 4
i directive (AD)thatis applicable to summarizing each FAA-public contad certain Airbus Model A310 and A300-concerned with the substana of this airplanes); and F/N*s B297AAM3, B297AAM4, B297AAMS, and 600 series airplanes.%is proposal proposal will be filed in the Rules B470AAM1(for Model A300-600 series would require that certain flight control Docket.
computers be snodified so that the Commenters wishing the FAA to airp, lanes).
ine French AD references Airbus tutopilot will dissagege whenever the acknowledge receipt of their mmmants Service Bulletins A310-22-W36, dated I
tirplane is in the "go-eround" mode.
submitted in response to this notice Dommber 14,1993 (for Wdel A310
- i
%1s prqsonalis by an must submit a self4ddinseed, stamped acciden' in the flight aew may postcard on which the following series airplanes), and A300-22-6021, Revision 1 dated December 24,1993 have attempted a
'-- H while the statement is made:" Comments to airplane was in an out.of-trim Docket Number 94-NM-145-AD." T1..
(for Model A300-600 series airplanes),
condition. no aretana speci6ed by the postcard willbe date stamped and as the ap sources of service
" AD are nnan iad to prevent returned to the mm'manter.
Informa ontoaccomplishthe 5
a F "'a==d controllability of the Availablisty of NPRMs f
B1 A3 0- 2 2036, I
i
$1 Any may obtain a copy of this dated December 14.1993, desi:ribes l
the = = =
h NFRM
=4-l'Hna a uest to the Promdures for modiScotton of only one 1
etabuiser and the elevator
}
DAMonunants must be nomived by ANhk-103, Attention: Rules Docket No. Installed on Model A310 series 9
Nowmber 38,1994' 94-NM+145-AD,1601 Lind Avenine, airplanes;while Alabus Sewice Bulletin
(
^""""***** Submit a=== ants in SW., Renton, Washington 96055-4056.
A300 c2-6021. Revision 1, dated i
Daramber 24,1993, describes 9
triplicate to the Federal Avia:.ica Macaselon a
l A
' ^ ^"- (FAA) Transport procedures for manlin tion of only one l
Airplane Directorate, ANM-103,
%e Dirodion Generale del' Aviation of the FCC's, PIN 8470AAM1,whichis j
Attentlen: Rules fiarbe No.94-NM-Civile (DGAC), whidiis the installed on Model A300-400 series 145-AD,160111ad Avenue,SW.,
aliw# " authority for France, lanas Upon accomplishment of this 4
ao.
modent= tion,the autopilot will J
Rentee. Washington 96055-4056.
recently noti 6ed the FAA that an unsaio Comments may be inspected et this-condition may exist on certain Airbus disengage whenever the airplane is in locetion between 900 a.m. and 3:00 Model A310 and A300-600 series the "go.eround" mode above 400 feet i.
. p.m., Monday through Friday, except airplanes %e French DGAC advises radio altitude and whenever the pilot Federal holidays.
that a Model A300-600 series lane attempts to override the autopilot by i
Informanian pertaining to this was recently involved in an acci t
exerting a artain amount of manual i
proposed rule may be obtained from or during which the flight crew may have force on the control column.
avaminedattheFAA Transport attempted a go-around while the
%1s airplane modelis manufactured Airplane Directorate Rules Docket, airplane was in ar. c ut-of-trim in France and is type certi6cated for 1601 Lind Avenue,SW., Renton, condition. Invest Vation into the cause, operation in the United States under the Wcshington.
of this out-of-trian wndition revealed provisions of section 21.29 of the l
l
.--m m.,
y
_,i-
_a-
_ _. I A D"B - 1 Federal Register / Vol. 60, No. 20 / Wednesday, February 8.1995 / Propos:d Rules
? DR.
7407 suspension. UDA projects that costly documents are not yet available and 1,1999. This proposalis another j
and inefficient movements of milk may not be available before the present component of the OCC's Regulation l
would have to be made to maintain pool comment period expires.
Review Program, which is intended to i
status of producers who have The Commission therefore intends to updato and streamlino OCC regulations historically supplied the market and to extend the comment period to allow a and to reduce unnecessary regulatory prevent disorderly marketing in the 75 day period after the staff guidance costs and other burdens. This action is Central Arizona marketing area.
documents becomo available to allow needed to climinate the rule when it i
I Accordingly,it may be appropriate to interested persons adequate timo to becomes obsolete, l
suspend the aforenid provisions comment on the staff guidance DATES: Comments must be received by beginning March t 1995, for an documents as well as the proposed rule. April 10,1995.
Indefinita period.
The comment period for this ADDRESSES: Comments should be List of Subjects in 7 CFR Part 11'i pr p sed rulo is bcIng extended to directed to: Communications Division, a
Milk marketing orders.
allow at least 75 days after the relevant Office of the Comptroller of the staff guidanco documents becomo The authority citation for 7 CFR Part available. At this time no firm Currency,250 E Street, SW, expiration dato is available. When the Washington, DC 20219, Attention:
1131 continues to read as follows:
Authority: Secs.1-19,48 Stat 31, as staff documents are available a notico Docket No. 95-01. Comments will be i
amended; 7 U.S.C. 601-674.
will be issued providing a firm available for public inspection and photocopy!ng at the same location.
Dated: February 2.1995.
i cxP ration dato for comments.
FOR FURTHER INFORMATION CONTACT:
t.on list amlya, ADDRESSES: Mall written comments to:
Andrew T. Cutlerrez. Attorney.
Adtninistrator.
Secretary, U.S. Nuclear Regulatory Legislativo and Regulatory Activitics l
IFR Doc. 95-314G Filed 2-7-95: 8:45 aml Commission. Washington, DC 20555, Division. (202) 874-5090.
situuo coor ms.ew S
M RY MORMANN:
nc De i e c mments o 1 55 Rockville Pike. Rockville. Maryland, Backgmund '
NUCLEAR REGULATORY between 7:45 am and 4:15 pm. Federal The OCC proposes to removo 12 CFR COMMISSIOfl w rkdays.
part 35 as a component ofits Regulation FOR FURTHER INFORMATION CONTACT: Dr.
Review Frogram. The goal of the 10 CFR Parts 50,52 and 100 Andrew J. Murphy. Office of Nuclear Regulation Review Program is to review i
RIN 3NM3 Regulatory Roscarch, U.S. Nuc! car all of the OCC's rules to reviso, Re ulatory Commission, Washington, streamline, and simplify them, and to Reactor Site Criteria including Selsmic DC 20555, telephone (301) 415-6010, climinato provisions that do not and Earthquake Engiacering Criteria concerning the scismic and carthquake contribute significantly to maintaining for Nuclear Power Plants and engineering aspects and Mr. Leonard the safety and soundness of national Proposed Denla! of Petition Fam Fre, Soffer Offico of Nuclear Regulatory banks or to accomplishing the OCC's Environment, Inc. et r!.
Research. U.S. Nuclear Regulatory other statutory responsibilitics.
i AGENCY: Nuclear Regulatory Commission, Washington, DC 20555, Titic VIII of the Competitive Equality Commission.
telephone (301) 415-6574, concerning Danking Act of 1987, Pub. L 100-80 other siting aspects.
101 Stat. 635 (1987), added 12 U.S.C.
ACTION: Proposed rule: Extension of Dated at Rockville, Maryland, this 3rd day 1823(j)in an atto'npt to alleviato some comment period.
of February 1995.
of the financial pressures then facing
SUMMARY
- On October 17,1994, the NRC Fode Nuckar bgulatory Commlulon.
agricultural banks. In particular,12 published (59 FR 52255) for public John C. Itoyle, U.S.C.1823(j) permits an agricultural comment a proposed revision of 10 CFR Arring Secretary ofthe comminion, bank to amortize over a period not to i
Parts 50,52, and 100 to update the IFR Doc. 95-3153 Filed 2-7-95: 8:45 aml exceed seven years:(1) Any loss on a i
qualified agriculturalloan that the bank criteria used in decisions regarding estuuo coor rsoo-ot-P power reactor siting. including geologic.
would otherwise be required to show on scismic, and carthquake engineering Its annual financial statement for any year between December 31,1983, and considerations for future nuc! car power DEPARTMENT OF THE TREASURY January 1,1992: and (2) any loss plants. The comment period for this proposed rule presently expires on Office of the Comptroller of the resulting from the reappraisal of February 14,1995.
Currency property that the bank owned or The Commission has received acquired between January 1,1983, and requests to extend the comment period 12 CFR Part 35 January 1,1992,in connection with a based on the fact that staff guidanco qualified agricultural loan. The OCC documents consisting of five draft (Cocket No. 95-01]
implemented this statutory provision by regulatory guides and three standard RIN 1557-AD44 promulgating 12 CFR part 35 with a review plcn sections that were t temporary rulo published on November accompany the proposed rule wero AgriculturalLoan Loss Amortization 2,1987 (52 FR 41959), and a final rulo delayed in issuance, and that published on July 28,1988 (53 FR AGENCY: Offico of the Comptroller of the 28373).
availability of these documents weto Currency Treasury.
Because the statute requires that a loss necessary to provide meaningful ACTION: Notico of proposed rulemaking, occur on or beforo December 31,1991, comments.
to qualify, and that the amortization The Commission agrees that
$UMMARY: The Office of the Comptroller period may not exceed seven years, the avai: ability of the staff guidance of the Currency (OCC) proposes to program becomes obsoleto on January 1, documents is necessary to provido remove its rulo governing agricultural 1999. Reflecting this fact, the OCC's rulo adequato comments. The staff guidanco loan loss amortization, effectivo January requires that loans bnder the program t<
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Proposed Rules Vol 60. No. 39 Tuesday, February 28, 1995 pontsnr. nottes to the puhhc of the propoW1. (Hyattsvilleh t301) 7344f"'1 plants. The comment period was to Thes secten of the FEDERAL REGISTER (F%rdale).
egire on February 14,1995.
Un February 8,1995, the Commiwinn mtuance of rules and regulatons. The S'.'*PLEMENTaRY INP')RMATION: On r.:ated !60 FF 74f;7) that it intended to january 23,1995. we putAisned m tim extend the comment period to allow to pa Federal Register (60 FR 4383-4389, interested persons adequate time to nan melang pihr to the % of the Anal Docket No. 9347fk-2) a proposal to Provide comments on staffguidance rules.
amend the Animal Welfare regulations documents consisting of five draft to establish standards for " swim.with.
regulatory guides and three standard DEPARTMENT OF AGRICULTURE the-dolphin" interactive programs.
review plan sections that were to Commats regarding the proposed Animal and Plant Health M;::M rule wens required to be received on or accompany the proposed rule, but were delayed in issuence.The Commission Serv 6ce before February 22,1995. During the stated 4 hat it would extend the comment comment period. we receis ed a request period 75 days aAer the staff guidance 9 CFR Ports 1 and 3 that we extend the comment period documents became available.
(Doetist No.98 476-4) beyond February 22. The requestor, a Availability nf the above staff -
marine mammal industry association.
guidana documents is being
~
stated that additional time is ner===ary
~~-
='in the Notices section of this to allow its membars to meet and to '
issue of the Federal Engister.The Animal Welfare; Marine Mommels formulate comments.
comment period for the proposed rule is aw.vt Animal nd Piant Health In response to this request, we are hereby extended to May 12,1995.
Inspection %vice, USDA.
extending the comment period for ACnose: Notice of extension of comment. Docket No. 93-076-2 through March 9 DATES:Conunant period now expires 1995.This will allow time for the May 12,1995. twnmman received aRer period.
requestor and other interested persons this date will be considered ifit is to develop comments on the proposed pr=r*=1to do so,but the Commission t pe od for pN I' *
'* ***" " *""'Id* " U " "'Y I#
rule comments receitvion or before this regarding the establishment oi standards Authority:7 U.S.C. 2131-2159; 7 CFR 2.17, date..
for " swim-with.the-dolphin" interactive 2.51, and 3n.2(g),
naam**asa' Mail written comments to:
programs.This extension, vill provide Done in Washington; DC. this 22nd day of Secretary, U.S. Nuclear Regulatory interested persons with additional time February 1995 Commission. Washington, DC 20555, ta prepare comments on the proposed Terry L Medley, Attention: Docketing and Service rule.
Acting Administrottar, AnimalandPlant Bd.
DATES: Consideration will be given only Mddnspecoon he.
nunen 5
to cori"nents on Decket No. 9'.nw,,
,, a L 9,5-.1881 Filed 2-27-45: 8:45.aml that are received on or before March 9, m m sw between 7:45 am and 4:15 pm, Federal 1995 ADontsets:Please send an original and
-- workdays. imay be submitted Comment three copies of your comments to Chief, NUCLEAR REGULATORY electronically.in either ASCII text or Regulatory Analysis and Development, COMMISSION Wordperfect format (version 5.1 or PPD, APHIS, USDA, P.O. Drawer 8t0, "later), by calling the NRC Electronic Riverdale, MD 20738. Please state that 10 CFR Ports 50,52 and 100 Bulletin Board (BBS) on FEDWORLD.
your comments refer to Docket No. 93-076-2. Comments received may be NN 3150-AD93
' %e bulletin board may be accomed witha personal computer, a modem, inspected at USDA, room 1141, South Reactor Site Crtterle including Seismic ud one of the commonly available Building,14th Street and Independence and Eartheguske Engir.eering Celterla communications software packages, or Ave. SW.,Washingtok, DC, between a for Nuclear Power Plants and directly via Internet. Certain background a.m. and 4:30 p.m., Monday through r.:; n Denial of Petition From Free dar==ents on the rulemaking are also Friday,except holidays. Persons Environment,Inc., et al.
available for downloading and viewing.
wishingto inspect comments am With a personalcomputer and requested to call ahead on (2021690-AGENCY: Nuclear Regulatory
' andem, the NRC rulemaking subsystem 2c17 to facilitate entry into the Commission.
can be. accessed on FEDWORLD, toll msnment reading an.
Acnost: Proposed rule; extension of free,by directly dialing 1.-800-303-N8Hmm tremeAnou CONTACT: Dr.
comment period.
9672.Cmagnunication software '
Barbara Kohn, Senior Staff Veterinarian,-
On Octobe* 17,1994, the NRC 3 -__ ^.should be set as follows:
AnimalCare Staff Regulatory suameAny:
parity to none, data bits to 8, and stop published (59 FR 52255) for public -
Enforcement and Animal Care, APHIS, comment a proposed revision of to CFR j hits to 4 (N,8,1k Using ANSI or VT-100 USDA,P.O. Drawer 810 Riverdale, MD terminalemulation,the NRC 20738.*!he telephone number for the parts 50,52, and 100 to update the -
rul==aWng subsystemcan be accessed agency cantare will changa when agency criteria used in decisions regardingpower reacto omcasIn Hyattaville,MD,snove to from thvNRC Main Menu." For further
~
Riverdale, MD, during February 1995.
seismic, and earthquake ' ngineering information about options avanable for e
i con Jerations for future nuclear power -
Telephone:(301) 436-7833
1i 1
Federal Rev,irter / Vol. so. No. 39 / Tuesday. Febniary 28. 1995 / Proposed Rul, s 10811 NRC at F"DWORI.D convolt tbn " Min' r r An 6 vWad -nri. "v'**
"'M k'" m, y,a adidav except
,,sd u information Center" f rom the "NetC obctrori!cally via the Electronic Bulletm p.m., Mondw throuhh P Win Mem"lV m y r!.m tr.d thi.
h.:d ALL.aud19 nil iustiu, r ederal nohdays. %#
"FEDWORLD Online User's Guides" rulemaking as indicated above.
The service information referenced in hejl iful.
FOR FURTHER INFORMATION CONTACT: Dr the proposed rule may be obtained from The NRC subsystem on FEDWORLD Andrew J. Murphy, Office of Nucbar Allied 5ignal Engines,550 Main Street.
also may be accessed directly by dialing Regulatory Research. U.S. Nuclear Stratford, CT 06497 telephone (203)
I 703-321-8020 for the rnain FEDWORLD flBS orby usingTelnet vialatemet-Regulatory Commission. Washington, 385-1470. This information may be -
ledworld gov. If 703-321-8020 is DC 20555; telephone (301) 4154010 examined at the FAA, New England
' dialed. the NRC subptm e an I" concerning the seismic and narthqu4,-
Region. Office of the Assistant Chief accessed frorn the main FEDWORLD
%immp p.edM1.ieuwd L.ounsel,12 INew t.ngland Executnu ge '::r.O"=c cf &cicar ut tv.,
% IMington, M A.
r j
menu first by selecting " Regulatory, Covernment Administration and State Research, U.S. Nuclear Regulatory i
FOR FURTHER INFO TION CONTACT:
Commission, Washington, DC 20555; g
" W gisee En n b.T otsieaknNkce,FAAgine 8P
~
In rmati u
I s lay HC 5 P
an option "U.S. Nuclear Regulatory.
er s t ng aspects, and Propeller Directorate,12 New i
Commission" that willlead to the NRC (5 UlS.C. 55a(a))
England Executive Park. Burlington, MA 7
Online main menu.The NRC Onlino Dated at Rockville. Maryland, this 22nd 01803-5299: telephone (617) 238-7148, fB
' area also may be accessed directly by day of February 1995.
fax (617) 238-7199.
if typing "/go nrc" at a FEDWORLD For the Nuclear Regulatory Commission I '
command line. If NRC is accessed from lohn C. Hoyle',
SUPPt.EMENTARY INFORMATION:
FEDWORLD's main m ", one may Acting See etaryof the Comns, ion.
Comments Invited return to FEDWORLD by selacting the (FR Doc. 95-4872 Filed 2-;;-15: a:45 aml
" Return to FEDWORLD" option from Interested persons are invited t'o so.mo coot reew-e participate in the making of the the NRC Online MainMenu. If NRC a'.
proposed rule by submitting such FEDWORLD is accessed via NRC's toll-written data, views, or arguments as
. free number, full access will be DEPARTMENT OF TRANSPORTATION they may desire. Communications available to all NRC systems, but thero should identify the Rules Docket will be no access to the main Federal Aviation Administration FEDWORLD system.
number and be submitt'ed in triplicate to if FEDWORLD is contacted using 14 CFR Part 39 the address speci6ed above. All s
Telnet, the NRC area and manus will be communications received on or before j
available, including the Rules Menu-(Dochet No. 94-ANE-68]
the closing date for comments, specified While documents may be downloaded -
Airworthiness Directives; Textron above, will be considered before taking action on the proposed Anle.The and mdssages lejt it is.not possible to Lycoming ALF502LSeriesTurbofan proposals contained ia this notice may l
write enemanipt upload files -
Engines oe chan using FW. all fi.es can be accessed and AGENCY: Federal Aplation in light of $be comments (cx>mments). If PT,DWORLD is contacted
C' ' -
.trw-Commats are specificallylasrit.
. downloaded but uploads are not Administration, DOT.
the overall regulatory, economic, ed on poenible: a lis'. of files without their ACTION: Notice of proposed rulemaking descriptions (normal Copher look) will (NPRML endmnantal, and energraspeds of be seen. An index file listing all files the proposedfule. All:cmainents SumuARY:This document proposes the - submitted will be'available, both before 9
&n a subdiactory, with
, descriptions;is available. Them is a 15 adoption of a new airworthiness and alter the closing date Asr asuments.
directive (AD) that is applicable to in the Rules Doeket forexamination by lb tl R a mEy be Textron Lycpming ALF502L series interested pessoas. A report
- i accessed thro the World Wide Web' ' turbofan engines. This proposal would summarizing esch FAA-pddse' contact establish reduced retirement life limits concerned with the substance of this -
I ad not d I
br stage 1 and stage F7 e *
,and Docket. <
ressor pmposal wm be HMn se Rules i
disks, and stage 2 turbine Rules Menu.Ucanation on NRC bulletin Provide a drawdown echadule for disks
.wa For more I oards callMr. Arthur Davis, Systems.
already beyond the reduced retirement Commenters wishina tlpe F.AA,to I
.[
.ntegrationend Development Branch.
Iffe limita,'llais p is 'prorgped,by; ackmoyledge sp<.gaJ their aa==*a s subminedin resposeptathismottpe r
'6 UA. Nuclear Regulatory Commission; nw 11 yees these camponents mustsuM eelf addr6ssed; smanped' 3
[,
Wasbiagton, DC 20555 lele9 hone (301t,'11sh actions 8edby the prom t d on which'ths which cou!d result in, vent disk idlure. ppos carstatemen
. AD are inted, to pa
~
. I' "
-415-6780;e-mail AXD3enre.govy
====*= to Single les of the proposed rule.
an inflight.eogine. Docket. Number 9MNIH6." The,
A.
may be by written re l'
telefax (301-50&2280) from., quest or. shu'tdown and edensive engi,ne, damage, postcard willhet 1
Comm5nts must be received by DATES:
Distelimtion Services. Printing and Mail letay 1.,1915..
mturned to thegouunenter..g AvailabilIliy ofNFIt0s,"
Services Brandi,OfRoe of c maaaaaaa** Submit comments in
- .Any
' 1may obtain a copy of this Administration.U.S. Nucieeritegulatory, pipliante tothe Federal Aviation :
Co==i== Ion, Washington, DC 20555..,' Ad=lal=*=*ian (FAA),New England e NPRM snha*tinga sequest to the
,j%
Daanmaats related to this rulensaking, Region.OtSco of the Asalarant Chief,,
FAA. New C Region; OfBce of the
=
includ ' camments received, may be Counsel, Attention: Rules Docket Nov
- AssistantChiegramaal. Ausation.
exis' at the NBC Public Document 94-ANIF-66,1214ew England Executive Rules Docket No.s4.<ANFe 66,12 New (s
Room ~2120 L Street NW. (Lower Level). Park. Burlington, MA 01803-52996 England Executiv's Park, Burlingt,ons MA l,
' Washington.,DC/linese some dncuments Comments may be inspected at this.
01803-5299..
\\ -
c l
N 3 "'I TD(L i
18mno Federal Reeister / W1. 60. No. 39 / Tuesday, February 28, 1995 / Notices
(
i l
NUCLEAR REGULATORY IXr-lon. "Researt ot Nuuear Power oi me connuuan cau.aw.
l COMMISSION Plant Shut Down by a Seismic Event,"
communications software patiages, m is being developed to provide guidance directly via Intemet Backgmund Draft Regulatory Guides and Standard acceptable to the NRC staff for documents on the rulemaking an al,o Review Plan Sections; issuance, performing inspections and tests of available for downloading and viewing Availability nuclear power plant equipment and on the bulletin board.
druduns pnono nn.t.ut of a plant that If using a personal computer :utd The Nuclear Regulatory Commission h
L, im <f 4-nW cm m 9 dnfo. of "Y m. hut,doyn by a,, seismic event modem. the NRC subsystem on w
ond m.wd 1%dWorld can ho ar e eswi dha in in five culdes niinned for its Regulatory 9m, 9
MNg&Mhumb1mL l
Guido Series along wilia diefia of dueu
.. General Site Sultability Cntena for 303-9672. Communications softwarc
)
welious of NUREG-0300. " Standard
. is bem8 parameters should be set as folion N"C1**# P **' b'*""*'
dance on the Parity to none, data bits to 8, and stop Review Plan for the Review of Safety degeloped to pmvide gui Antlysis Reports for Nuclear Power ma) r sue charactmstics mlated to the bits to 1 (N,8,1). Using ANSI or VT-t00 Plants." The Regulatory Guide Series public health and safety and terminal emulation, the NRC NUREGs has been developed to describe and env mnmentalissues that the NRC staff and RegCuides for Comment subsystems make available to the public such c nsiders m detenmmg the suitability can then be accessed by selecting the information as methods acceptable to ra t. t ndard {u s Men," option from the "NRC k
the NRC staff for implementing specific opos?e#d e Non 3 oi
. enu. For further nfermatton M
parts of the Commission's regulations-Review Plan Sectic.n 2.5.1, " Basic i "it options available for NRC at t".:hr.! pes used by the staff in Geologic and Seismic Inform. lon," -
reoW rid, consult the licip/
waluating specific problems or being developed to describ he kinds of In onnaum Center from the "NR(.,
pstulated accidents, and data needed basic geological, seismologi al. and Main Menu., Users will find the by the staff irrits review of applications p,,,nhysical information ar.d review FedWorld Onhne User,s Guide.
for permits and licenses.
ocedures necessary tr, evaluate a particularly helpful. Many NRC These draft guides and r -ri standard clear power station sita.
subsystems and databases also have a e
review plans are in support of proposed The Second Proposed Revishn 3 :.f
'""P ""f""?""."~ enter " opnon that amendments to 10 CFR parts 50,52, and Draft Standard Review Plan Section
!rular subsystem.
100 (59 FC 52255) that were proposed 2.5.2." Vibratory Ground Moaon."is The NRC subsystem on FedWorld can to update the criteria used in decisions being developed to describe proceduces niso be accessed by a direct dial phona regarding power reactor siting, to assess the ground motion potential of number for the main FedWorld BBS-iacluding geologic, seismic, and seismic sources at the site and to assess 703-321-8020:Telnet via internet:
earthquake engineering considerations the safe shutdown earthquake.
fedworld. gov (192.239.93.3h File for future nuclear power plants. The The Proposed Revision 3 of Draft Transfer Protocol (FTP) via Intemet draft guides are intended for Division 1.
Standard Review Plan Section 2.5.3.
fl.fedworld. gov (192.239.92.203h and P
' Power Reactors," and Division L
" Surface Faulting." is being developed World Wide Web using: http:n to describe the geosciences information www fedworld. gov (this is the Uniform
$nvironmental and Siting " d and review procedures neeried to assess Resource Locator (URL)).
DG-1932 " Identification an Characterization of Seismic Sources and the significance of faults to the If using a method other than the toll setermination of Safe Shutdown suitability of the site.
free number to contact Fedworid, the Earthquake Ground Motion," is being These ihafts are being issued to developed to provide general guidance involve the public in the early stages of NRC subsystem will be addressed from on procedures acceptable to the NRC the development of regulatory positions the main Fedworld menu by selecting station cond in these areas. These drafts have not the "F-Regulatory, Government geophysical, gicting geological, seismological, ! 'd received complete staff review and do Administration and State Systems /
geotechnical investigations; identifying not represent official NRC staff then selecting "A-Regulatory Information Mall." At that point, a and characterizing seismic sources; positions.
conducting probabilistic seismic hazard Public comments are being solicited
. menu will be displayed that has an analyses: and determining the safe on these drafts. Comments should be option "A-U S Nuclear Regulatory shutdown earthquake ground motion for accompanied by supporting data.
Commission" that will take you to the a nuclear power plant.
Written comments may be submitted to NRC Online main menu You can also DG-1033, the Third Proposed the Rules and Review and Directives
. go directly to the NRC Online area by Revision 2 to Regulatory Guide 1.12.
Branch Division of Freedo of typing "/co nic" at a FedWorld
" Nuclear Power Plant instrumentation Information and Publicati. Services, s.uno..-..
line If you access NRC from for Earthquakes," is being developed to Office of Administration, U.S. N.a '.
~ *
' Ps main menu, you may return describe seismic instrumention type.
Regulatory Commission Wasington, to FedWorld by selecting the " Return to location, operability, and characteristics DC 20555 Copies of comments received FedWorld" option from the NRC O that is acceptable to the NRC staff for may be examined at the NRC Public Main Menu llowever,if you access
'i satisfying the requirements of the Document Room,2120 L Street, NW.,
NRC at Fedworld by using NRC's toll-l Commission's regulations.
Washington DC. Comments willbe free number, you will have full access DG-1034," Pre-Earthquake Planning most helpful if received by May 12.
to all NRC systems but you will not have access to the main FedWorld and Immediate Nuclear Power Plant 1995 Operawr Postearthquake Actions,"is Comments may be submitted system. For more information on NRC l
being developed to provide guidance electronically,in either ASCII text or bulletin boards call Mr. Arthur Davis.
Wordperfect format (versica 5.1 or Systems Integration and Development tcceptable to the NRC staff for a timely I
evaluation after an earthquake of the later), by calling the NRC Electronic Branch, U.S. Nuclear Regulatory recorded seismic instrumentation data Bulletin Board on FedWorld.The Commission, Washington, DC 20555, and to determine whether plant bulletin board may be accessed using telephone (301.) 415-5780; e-mail shutdown is required.
personal computer, a modem. and one AXD3@nre. gov l
an.
Federal Register / Vol. tio, No. 39 / Tuesd.iy, February 28,1995 / Not es 10881 l
Although a time limit is given for Commission's rules uad reuuhtiont nanelio can<lirides proWM W "-
i.usmuunt ou these-draf ts, comments ine Comrmss on has made appropriate Article 8 of the Understanding on Rules and suggestions in connection with fmdings as required by the Act and the and Procedures Governing the itams for inclusion in guides or standard Commission's rules and regulations in Settlement of Disputes (DSUI and in the review plan sections or irnprovements to CFR Chapter h which are set fortl. !n Decision on Certain Dispute Settlement in all published documents are the license amendment.
Procedures for the General Agreement i
oncouraged at any time.
Nritice of Con.,ideration of Issuance of on Trade in Services (GATS) of the Regulatory gisiiles anti tire Staind;ird Ame! idment sind Opportunity for World Trade Organization (WTO).
Review Plan are availabic for inspection IIcaring in connection wilh this m tio,i at !!m Com:wWo.2 :%... L.,, a,:
.. pd'.hu.i m um fedcra! Mc ;utu SUMMAHf: 't he D5U provides a l
Rnnml717n I. street. NW. W hingt-no ApH 1?. mod, f 50 FP F401) ad
,,,,;.& nim for the :.cttlemem of DC. Requests for single copies of draft April 21,1994.159 FR 19031). No disputek among members of the WTO. A documents (which may be reproducedJ request for a hearing or etition for
, three-perphp panel conducts escli "
or for placement on an automatic leaye to intervene was ed following
' dispute settlement proceeding and distributiori list for single copies of this notice.
issues a report for consideration by the 1
future draft guides in specific division The Commission has prepared an' Dispute Settlement Body (DSB)in should be made in writing io the U.S.
Envaronmental Assessment related to
. Nuclear Regulatory Commission, the action and has determined not t which representatives of all WTO l
members participate.
Wa61ngton, DC 20555, Attention:
Prepare an environmentalimpact l
Dis db:
t and Mail Services Section, statement. Based upc t the Section 123(b) of the Uruguay Round Telephone requests cannot be environmental assessment, the Agreements Act (URAA), Public Law accommodated. Rm;ulatory uides and Comnussion has concluded that the 103-405, pmvides that the Trade standard review plans are n issuance of this amendment will not
. Representative shall seek to ensu e that copyrighted, and Commission approval have a significant effect on the quality persons appointed to the WTO roster are well is not required td reprod' ce them.
f the human environment (60 FR 8739.
M1ualified and that the roster u
dated Februa 15,-1995).
Pe db bdd is U.S.C. 552(a))
For further etails with respect to the the subiect matters covered by the n,..,1,, u.a.m m-.. rind, this 13 day action see (1) the application for Umguay Round Agreements. USTR uf Febsuary 1995, amendment dated October 15,1993, and invites citizens of the United States with j
For the Nuclear Regulatory Cos namon.
supplemented by letters dated April 15, appropriate qualifications to apply for themis P. Speis.
and November 10,1994,'and February consideration as a nominee to the rostor DeputyDirector. OfficeofNuchar Regulatory 10 and 14,1995 (2) Amendment No.
. - DATES: Eligible citir. ens are encouraged Research.
120 to License No. NPF-29, (3) the to apply by April ~10,1995 to b6 j
IFR Doc. 954873 Filed 2-27ws; BA5 aml Commission's related Safety Evaluation, considered for nomination to the mster suo caos rs
.u and (4) the Commission's in 1995.
Environmental Assessrnent. Allof these FOR FURTHER INFOHttATION CONTACT:
(Docket No. 50-416]
items are available for,public inspection For information conceming the form of at the Commission's Public Document the application, contact Sybia liarrison, Energy Operations, Inc. et al.; Notice of Room, the Gelman Building,2120 L Legal Assistant, Office of the General issuance of Amendment to Facility Street NW., Washington, DC 20555, and Counsel,(202) 395-3432. For '
Operating License at the local public documeni.oom information conceming WIlO located at the Judge George W procedures or the duties involved, The L*,':. Nuclear Regulatory Armstrong Library, P.O. Box 1406, S*
contact Catherine Field, Associate Commission (Commission) has issued Commerce at Washington, Natchez, General Counsel, (202) 395-3432, or Amendment No.120 to Facility Mississippi 39120 Mark Linscott, Office of GATTlWTO Operating License No. NPF-29 issued to D.ited at Rockville Maryland, this 21st dav Affairs, (202) 395-3063 Forinformation Energy Operations, Inc. (the licensee),
of February 1995 -
which revised the Technical relating to the GATS, contact Vanessa For the Nuclear Regulatory Commission.
Sciarra, Assistant General Counsel, Specifications for operation of the william D. Beckner, Grand Gulf Nuclear Station, Unit 1, (202) 3954-7305 or Richard Self, Deputy osrector, Project Directora te IV-1. Division Assistant USTR for Services,(202) 395-located in Claibome County,,
of Reactor Pmjects illN,0ffice of Nuclear 45}0, S.
Mississi
- 1. The amendment is effective Reactor Regulation.
as of th te'ofIssuance.
IFR Doc. 95-4871 File.12-27-95; a:45 ami The amendment modified the to Article 8 of the DSU thewTO technical specifications by replacing the Secretariat is to maintain en indicative existingtechnical specificatwns in their list of welliqualifed governnfental and
. entirety with a new set of te'chnical OFFICE OF THE UNITED STATES
"# 8 **"""*" * "
specifications based on NUREG-1434; including persas who have served on TRADE REPRESENTATIVF-
" improved BWR-6 Technical or resanted,a case to a panel, taught or Specifications," dated September 1992.
Notice of Opportunity To Apply For Pu lished on international trade law or This amendment was based on the Nomination to the Wottd Trade Pob,ey, or served as a senior tsado pohcy
, licensees submittal of October 15,1993, Organization Diepute Settlement flicial of a WTO member country The as supplemented by letters dated April Rosters of Panel Candidates indicative list will be used to assist in 15, and November 10,1994, and the selection of panelists for dispute February to and 14,1995 AGENCY: Office of the United States settlement. proceedings. Panel meshbers The application for the amendment Trade Representative.
are to be selected with & view to complies with the standards and.
ACTION: Notice of opportunity to apply ensuring a sufficiently div.erse requirements of the~ Atomic Energy Act a, for nomination by the United States to backgmund and a wide spectrum of 1
of 1954, as amended (the Act) and the ' indicative lists of non-governmental expenence.
l NP9 3 d j
\\
U.S. NUCLEAR REGULATORY COMMISSION February 1995 f
(~N OFFICE OF NUCLEAR REGULATORY RESEARCH Division 1 i
Task DG-1034 I
S DRAFT REGULATORY GUIDE e...+
Contact:
R.M. Kenneally (301)415-6303 1
DRAFT REGULATORY GUIDE DG-1034 2
(Previously Issued as Draft DG-1017) l 3
PRE-EARTHQUAKE PLANNING AND IMNEDIATE NUCLEAR POWER i
4 PLANT OPERATOR POSTEARTHQUAKE ACTIONS
]
5 A.
INTRODUCTION i* 3 riteria for 6
Paragraph IV(a)(4) of Proposed Appendix S, " Earthquake Engi C
7 Nuclear Power Plants," to 10 CFR Part 50, " Domestic Licensing etkand 8 Utilization Facilities," would require that suitable instru.n provided so 9
that the seismic response of nuclear power plant feature ' m tin $tosafetycanbe 10 evaluated promptly. Paragraph IV(a)(3) of Proposed nd %S 10 CFR Part 50 would 11 require shutdown of the nuclear power plant if vi t
ou d motion exceeding that 12 of the operating basis earthquake ground moti gnificant plant damage 13 occurs. If systems, structures, or componen ce ry for the safe shutdown of the
(
) 14 nuclear power plant would not be availa currence of the OBE, the licensee 15 would be required to consult with t,
C opose a plan for the timely, safe 16 shutdown of the nuclear power plan :
P os Paragraph 50.54(ff) to 10 CFR Part 50 hlantsthathaveadoptedtheearthquake 17 would require licensees of n r
18 engineering criteria in Pro ed endix S to 10 CFR Part 50 to shut down the plant if 19 the criteria in Paragraph IV(
f Proposed Appendix S are exceeded.
20 This guide i being developed to provide guidance acceptable to the NRC staff for 21 a timely evalua er an earthquake of the recorded instrumentation data and for sees vg y 22
'u
.ance.s being developed in Draft Regulatory Guide DG-1033, the Third hi. 'on 2 to Regulatory Guide 1.12, " Nuclear Power Plant Instru-23 Pr e
24 me to Earthquakes," to describe seismic instrumentation acceptable 25 to RC staff.
This regulatory guide le being leeued in draft form to involve the public in the early stages of the development of a regulatory position in this area. It has not received complete staff review and does not represent an official NRC staff position.
Public comments are being solicited on the draft guide (including any implementation schedule) and its associated regulatory analysis or l
value/ impact statement. Comments should be accompanied by appropnete supporting data. Written comments may be submitted to the Rulee l
Review and Directives Branch, DFIPS, Office of Administration, U.S. Nuclear Reguistory Commission, Weehington, DC 20555. Copies of I
commente received may be examined at the NRC Public Document Room,2120 L Street NW., Washington, DC. Comments will be moet helpful l
if rec.iv.d by May 12, 1995.
Requests for eingle copies of draft guides (which may be reproduced) or for placement on an automatic distribution liet for eingle copies of r
future guides in specific divisiona should be made in writing to the U S. Nuclear Regulatory Commission, Washington, DC 20555, Attention:
Office of Administration, Distribution and Mail Services Section.
(
I)J b 9
4%o Ob0119 b.
I determining whether plant shutdown would be required by the proposed 2
amendments to 10 CFR Part 50.
3 Regulatory guides are issued to describe and make available to the 4
public such information as methods acceptable to the NRC staff for implement-5 ing specific parts of the Commission's regulations, techniques used by the 6
staff in evaluating specific problems or pm.tulated accidents, and guidance to 7
applicants. Regulatory guides are not substitutes for regulations, and 8
compliance with regulatory guides is not required.
Regulatory guides are 9
issued in draft form for public comment to involve the public in the early 10 stages of developing the regulatory positions. Draft regulatory guides have 11 not received complete staff review and do not represent official NRC staff 12 positions.
13 Any information collection activities mentioned in this draft regulatory 14 guide are contained as requirements in the proposed amendments to 10 CFR Part 15 50 that would provide the regulatory basis for this guide. The proposed 16 amendments have been submitted to the Office of Management and Budget for 17 clearance that may be appropriate under the Paperwork Reduction Act.
Such 18 clearance, if obtained, would also apply to any information collection 19 activities mentioned in this guide.
20 B.
DISCUSSION 21 When an earthquake occurs, ground motion data are recorded by the 22 seismic instrumentation.' These data are used to make a rapid determination 23 of the degree of severity of the seismic event. The data from the seismic 24 instrumentation, coupled with information obtained from a plant walkdown, are 25 used to make the initial determination of whetter the plant must be shut down, 26 if it has not already been shut down by operational perturbations resulting 27 from the seismic event.
If on the basis of these initial evaluations 28 (instrumentation data and walkdown) it is concluded that the plant shutdown 29 criteria have not been exceeded, it is presumed that the plant will not be 30 shut down.
Guidance is being developed on postshutdown inspections and plant 31 restart; see Draft Regulatory Guide DG-1035, " Restart of a Nuclear Power Plant j
32 Shut Down by a Seismic Event."
j The Electric Power Research Institute has developed guidelines that will 33 34 enable licensees to quickly identify and assess earthquake effects on nuclear 2
. _ _ _ _ _.m 1
power plants. These guidelines are in EPRI NP-5930, "A Criterion for Deter-2 mining Exceedence of the Operating Basis Earthquake," July 1988';
l i I l
3 EPRI NP-6695, " Guidelines for. Nuclear Plant Response to an Earthquake,"
4 December 1989'; and EPRI TR-100082, " Standardization of Cumulative Absolute 5
Velocity," December 1991.*
l 6
-This regulatory guide is based on the assumption that the nuclear power 7
plant has operable seismic instrumentation, including the equipment and soft-l 8
ware required to process the data within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after an earthquake. This is 9
necessary because the decision to shut down the plant will be made, in part, 10 by comparing the recorded data against OBE exceedance criteria. The decision 11 to shut down the plant is also based on the results of the plant walkdown 12 inspections that take place within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of the event.
If the seismic 13 instrumentation or data processing equipment is inoperable, the guidelines in l
14 Appendix A to this guide would be used to determine whether the OBE has been 15 exceeded.
16 Because earthquake-induced vibration of the reactor vessel could lead to 17 changes in neutron fluxes, a prompt check of the neutron flux monitoring 18 sensors would provide an indication that the reactor is stable.
19 Shutdown of the nuclear power plant would be required if the vibratory
'(
20 ground motion experienced exceeds that of the OBE. Two criteria for determin-21 ing exceedance of the OBE (based on data recorded in the free-field) are 22 provided in EPRI NP-5930: a threshold response spectrum ordinate criterion and 23 a cumulative absolute velocity (CAV) criterion. Seismic Category I structures 24 at the nuclear power plant site may be designed using different ground motion 25 response spectra; for example, one used for the certified standard design and 26 another for site-specific applications. The spectrum ordinate criterion is 27 based on the lowest spectrum used in the design of the Seismic Category I 28 structures. A procedure to standardize the calculation of the CAV is provided j
29 in EPRI TR-100082. A spectral velocity threshold has also been recommended by 30 EPRI since some structures have fundamental frequencies below the range speci-31 fied in EPRI NP-5930. The NRC staff now recommends 1.0 to 2.0 Hz Tor the 32 range of the spectral velocity limit since some structures have fundamental l
33 frequencies below 1.5 Hz. The former range was 1.5 to 2.0 Hz.
l 1
34
- EPRI reports may be obtained from the Electric Power Research Institute, Research l
35 Reports Center, P.O. Box 50490, Palo Alto, CA 94303 3
l
(
=
i 1
Since the containment isolation valves may have malfunctioned during an 2
earthquake, inspection of the containment isolation system is necessary to 3
ensure continued containment integrity.
4 The NRC staff does not endorse the philosophy discussed in EPRI NP-6695, 5
Section 4.3.4 (first paragraph, last sentence), pertaining to plant shutdown 6
considerations following an earthquake based on the need for continued power 7
generation in the region.
If the licensee determines that plant shutdown is 8
required by the NRC's regulations, but the licensee does not consider it 9
prudent to do so, the licensee would be required to consult with the NRC and 10 propose a plan for the timely, safe shutdown of the nuclear power plant.
11 Appendix B to this guide provides definitions to be used with this 12 guidance.
13 Holders of an operating license or construction permit issued prior to 14 the implementation date to be specified in the active guide may voluntarily 15 implement the methods to be described in the active guide and the methods 16 being developed in Draft Regulatory Guides DG-1033, " Nuclear Power Plant 17 Instrumentation for Earthquakes," and DG-1035, " Restart of a Nuclear Power 18 Plant Shut Down by a Seismic Event."
19 C.
REGULATORY POSITION 20 1.
BASE-LINE DATA 21 1.1 Jnformation Related to Seismic Instrumentation 22 A file containing information on all the seismic instrumentation should 23 be kept at the plant.
The file should include:
24 1.
Information on each instrument type such as make, model, and 25 serial number; manufacturers' data sheet; list of special features or options; 26 performance characteristics; examples of typical instrumentation readings and 27 interpretations; operations and maintenance manuals; repair procedures (manu-28 facturers' recommendations for repairing common problems); and a list of any l
29 special requirements, e.g., maintenance, cperational, installation.
l l
l 9
4
I l'
2.
Plan views and vertical sections showing the location of each
?.
seismic instrument and the orientation of the instrument axis with respect to 3
a plant reference axis.
4 3.
A complete service history of each seismic instrument. The l
5 service history should include information such as dates of servicing, 6
description of completed work, and calibration records and data (where 7
applicable).
8 4.
A suitable earthquake time-history (e.g., the October 1987
.i 9
Whittier, California, earthquake) or manufacture's calibration standard and
.10 the corresponding response spectrum and cumulative absolute velocity (CAV) i 1
11 (see Regulatory Position 4). The response spectrum and CAV should be 12 calculated after the initial installation and each servicing of the free-field l
13 instrumentation.
l 14 1.2 Plannina for Postearthauake Inspections 15 The selection of equipment and structures for inspections and the 16 content of the baseline inspections as described in Sections 5.3.1 and 5.3.2.1 17 of EPRI NP-6695, " Guidelines for Nuclear Plant Response to an Earthquake," are 18 acceptable to the NRC staff for satisfying the proposed requirements in 19 Paragraph IV(a)(3) of Proposed Appendix S to 10 CFR Part 50 for ensuring the 20 safety of nuclear power plants.
21 2.
IMMEDIATE POSTEARTHOUAKE ACTIONS i
l.
22 The guidelines for immediate postearthquake actions specified in 23 Sections 4.3.1 (with the exception specified below) and 4.3.2 (including 24 Section 5.3.2.1 and items 7 and 8 of Table 5-1) of EPRI-NP-6695 are acceptable 25 to the NRC staff for satisfying the requirements proposed in Paragraph 26 IV(a)(3) of Proposed Appendix S to 10 CFR Part 50.
27 In Section 4.3.1, a check of the neutron flux monitoring sensors for 28 changes should be added to the specific control room board checks.
5 1
1 3.
EVALUATION OF GROUND MOTION RECORDS 2
3.1 Data Identification 3
A record collection log should be maintained at the plant, and all data 4
should be identifiable and traceable with respect to:
5 1.
The date and time of collection, 6
2.
The make, model, serial number, location, and orientation of the 7
instrument (sensor) from which the record was collected.
8 3.2 Data Collection 9
3.2.1 Only personnel trained in the operation of the instrument shuuld 10 collect the data.
11 LL2 The steps for removing and storing records from each seismic 12 instrument should be planned and performed in accordance with established 13 procedures.
14 3.2.3 Extreme caution should be exercised to prevent accidental damage 15 to the recording media and instruments during data collection and subsequent 16 handling.
17 3.2.4 As data are collected and the instrumentation is inspected, notes 18 should be made regarding the condition of the instrument and its installation, 19 for example, instrument flooded, mounting surface tilted, fallen objects that 20 struck the instrument or the instrument mounting surface.
21 3.2.5 For validation of the collected data, the information described 22 in Regulatory Position 1.1(4) should be added to the record without affecting
)
23 the previously recorded data.
24 3 M If the instrument's operation appears to have been normal, the 25 instrument should remain in service without readjustment or change that would 26 defeat attempts to obtain postevent ca.libration.
6 l
1 3.3 Record Evaluation
-2 Records should be analyzed according to the manufacturer's specifica-3 tions and the results of the analysis should be evaluated. Any record 4
anomalies, invalid data, and nonpertinent signals should be noted, along with 5
any known causes.
6 4.
DETERMINING OBE EXCEEDANCE J
l 7
The evaluation to determine whether the OBE was exceeded should be 8
performed using data obtained from the three components of the free-field 9
ground motion (i.e., two horizontal and one vertical).
The evaluation may be 10 performed on uncorrected earthquake records.
It was found in a study of 11~
uncorrected versus corrected earthquake records (see EPRI NP-5930) that the I
12 use of uncorrected records is conservative. The evaluation should consist of 13 a check of the response spectrum, CAV limit, and the operability of the 14 instrumentation. This evaluation should take place within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of the 15 earthquake.
16 4.1 Response Spectrum Check 17 4.1.1 i
18 The OBE response spectrum check is performed using the lower of:
l 19 1.
The spectrum used in the certified standard design, or 20 2.
A spectrum other than (1) used in the design of any Seismic f
21 Category I structure.
l 22 4.1.2 23 The OBE response spectrum is exceeded if any one of the three components 24 (two horizontal and one vertical) of the 5 percent damped free-field ground
[
25 motion response spectra is larger than:
7
,-,--.n,-..
a d
1 1.
The corresponding design response spectral acceleration (0BE l
2 spectrum if used, otherwise 1/3 of the safe shutdown earthquake 3
(SSE) spectrum) or 0.29, whichever is greater, for frequencies i
4 between 2 to 10 Hz, or 5
2.
The corresponding design response spectral velocity (OBE spectrum 6
if used, otherwise 1/3 of the SSE spectrum) or a spectral velocity 7
of 6 inches per second (15.24 centimeters per second), whichever 8
is greater, for frequencies between 1 and 2 Hz.
9 4.2 Cumulative Abiolute Velocity (CAV) Limit 10 For each component of the free-field ground motion, the CAV should be 11 calculated as follows:
(1) the absolute acceleration (g units) time-history 12 is divided into 1-second intervals, (2) each 1-second interval that has at 13 least 1 exceedance of 0.025g is integrated over time, (3) all the integrated 14 values are summed together to arrive at the CAV. The CAV limit is exceeded if 15 any CAV calculation is greater than 0.16 g-second. Additional information on 16 how to determine the CAV is provided in EPRI TR-100082.
17 4.3 Instrument Operability Check 18 After an earthquake at the plant site, the response spectrum and CAV 19 should be calculated using the calibration standard (see Regulatory Position 20 1.l(4)) to demonstrate that the time-history analysis hardware and software 21 were functioning properly.
22 4.4 Inocerable Instrumentation or Data Processina Hardware or Software 23 If the response spectrum and the CAV (Regulatory Positions 4.1 and 4.2) 24 can not be obtained because th^3 seismic instrumentation is inoperable, data 25 from the instrumentation are destroyed, or the data processing hardware or 26 software is inoperable, the criteria in Appendix A to this guide should be 27 used to determine whether the OBE has been exceeded.
l l
O 8
i 1
5.
CRITERIA FOR PLANT SHUTDOWN 2
If the OBE is exceeded or significant plant damage occurs, the plant 3
must be shut down unless a plan for the timely, safe shutdown of the nuclear 4
power plant has been proposed by the licensee and accepted by the NRC staff.
5 5.1 OBE Exceedance 6
If the response spectrum check And the CAV limit (performed or 7
calculated in accordance with Regulatory Positions 4.1 and 4.2) were exceeded, 8
- the OBE was exceeded and plant shutdown is required.
If either limit does not 9
exceed the criterion, the earthquake motion did not exceed the OBE.
If only 10 one limit can be checked, the other limit is assumed to be exceeded. The 11 determination of whether or not the OBE has been exceeded should be performed i
12 even if the plant automatically trips off-line as a result of the earthquake.
13 5.2 Damaae l
14 The plant should be shut down if the walkdown inspections performed in 15 accordance with Regulatory Position 2 discover damage. iiiis evaluation should 16 take place within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of the earthquake occurrence.
L 17 5.3 Continued Ooeratign 18 If the OBE was not exceeded and the walkdown inspection indicates no l
19 damage to the nuclear power plant, shutdown of the plant is not required' The 20 plant may continue to operate (or restart following a post-trip review, if it 21 tripped off-line because of the earthquake).
22 6.
PRE-SHUTDOWN INSPECTIONS 23 The pre-shutdown inspections described in Section 4.3.4 (including all 24 subsections) of EPRI NP-6695, " Guidelines for Nuclear Plant Response to an 25 Earthquake," with the exceptions specified below are acceptable to the NRC j
26 staff for satisfying the requirements proposed in Paragraph IV(a)(3) of 27 Proposed Appendix S to 10 CFR Part 50 for ensuring the safety of nuclear power 28 plants.
9 L
1 6.1 Shutdown Timina 2
Delete the last sentence in the first paragraph of Section 4.3.4.
3 6.2 Safe Shutdown Eouioment 4
In Section 4.3.4.1, a check of the containment isolation system should 5
be added to the minimum list of equipment to be inspected.
6 6.3 Orderly Plant ShdtdoWn 7
The following paragraph in Section 4.3.4 of EPRI NP-6695 is printed here 8
to emphasize that the plant should shut down in an orderly manner.
9
" Prior to initiating plant shutdown following an earthquake, 10 visual inspections and control board checks of safe shutdown 11 systems should be performed by plant operations personnel, and the 12 availability of off-site and emergency power sources should be 13 determined. The purpose of these inspections is to determine the 14 effect of the earthquake on essential safe shutdown equipment 15 which is not normally in use during power operation so that any 16 resets or repairs required as a result of the earthquake can be 17 performed, or alternate equipment can be readied, prior to 18 initiating shutdown activities.
In order to ascertain possible 19 fuel and reactor internal damage, the following checks should be 20 made, if possible, before plant shutdown is initiated.... "
21 D.
IMPLEMENTATION 22 The purpose of this section is to provide guidance to applicants and 23 licensees regarding the NRC staff's plans for using this regulatory guide.
24 This proposed revision has been released to encourage public.
25 participation in its development.
Except in those cases in which the 26 applicant proposes an acceptable alternative method for complying with the 27 specified portions of the Commission's regulations, the method to be described l
28 in the active guide reflecting public comments will be used in the evaluation 29 of applications for construction permits, operating licenses, combined
[
l 10 i
(
j
{
1 licenses, or design certification submitted after the implementation date to 2
be specified in the active guide. This guide would not be used in the i
3 evaluation of an application for an operating license submitted after the l
4 implementation date to be specified in the active guide if the construction j
5 permit was issued prior to that date.
1 O
O 11
1 1
APPENDIX A 2
INTERIM OPERATING BASIS EARTHQUAKE EXCEEDANCE GUIDELINES 3
This regulatory guide is based on the assumption that the nuclear power 4
plant has operable seismic instrumentation and equipment (hardware and 5
software) to process the data.
If the seismic instrumentation or data 6
processing equipment is inoperable, the following should be used to determine 7
whether the operating basis earthquake ground motion (0BE) has been exceeded; l
l 8
1.
For plants at which instrumentally determined data are available only
)
l 9
from an instrument installed on a foundation, the cumulative absolute 10 velocity (CAV) limit (see Regulatory Position 4.2 of this guide) is not l
11 applicable.
In this case, the determination of OBE exceedance is based 12 on a response spectrum check similar to that described in Regulatory 13 Position 4.1 of this regulatory guide. A comparison is made between the 14 foundation-level design response spectra and data obtained from the
)
15 foundation-level instruments.
If the response spectrum check at any 16 foundation is exceeded, the OBE is exceeded and the plant must be shut l-17 down. At this instrument location it is inappropriate to use the 0.2g 18 spectral acceleration limit or the 6 inches per second (15.24 19 centimeters per second) spectral velocity limit stated in Regulatory 20 Position 4.1.2.
21 2.
For plants at which no free-field or foundation-level instrumental data 22 are available, gr the data processing equipment is inoperable and the 23 response spectrum check and the CAV limit can not be determined 24 (Regulatory Positions 4.1 and 4.2), the OBE will be considered to have 25 been exceeded and the plant must be shut down if one of the following 26 applies:
27 1.
The earthquake resulted in Modified Mercalli Intensity (MMI) VI or l
28 greater within 5 km of the plant, i
l 29 2.
The earthquake was felt within the plant and was of magnitude 6.0 30 or greater, or 31 1
A-1 l
i
1 3.
The earthquake was of magnitude 5.0 or greater and occurred within
'2 200 km of the plant.
3 A postearthquake plant walkdown should be conducted (see Regulatory 4
Position 2 of this guide).
5 If plant shutdown is warranted under the above guidelines, the plant 6
should be shut down in an orderly manner (see Regulatory Position 6 of this 7
guide).
8 Note: The determinations of epicentral location, magnitude, and 9
intensity by the U.S. Geological Survey, National Earthquake 10 Information Center, will usually take precedence over other estimates; 11 however, regional and local determinations will be used if they are 12 considered to be more accurate. Also, higher quality damage reports or 13 a lack of damage reports from the nuclear power plant site or its 14 immediate vicinity will take precedence over more distant reports.
O O
A-2
_..-____._m i
J 1
APPENDIX B 2
DEFINITIONS 3
Certified Standard Desion. A Commission approval, issued pursuant to Subpart l
4 B of 10 CFR Part 52, of a standard design for a nuclear power facility.
i 5
Desian Response Spectra.
Response spectra used to design Seismic Category I l
6 structures, systems, and components.
7 Qoeratina Basis Earthauake Ground Motion (0BE).
The vibratory ground motion f
8 for which those features of the nuclear power plant necessary for continued 9
operation without undue risk to the health and safety of the public will l
10 remain functional. The value of the OBE is set by the applicant.
I 11 Soectral Acceleration.
The acceleration response of a linear oscillator with 12 prescribed frequency and damping.
13 Spectral Velocity. The velocity response of a linear oscillator with pre-scribed frequency and damping.
O 14 O
B-1
.m n
1 REGULATORY ANALYSIS i
2 A separate regulatory analysis was not prepared for this regulatory 3
guide. The draft regulatory analysis, " Proposed Revisions of 10 CFR Part 100 4
and 10 CFR Part 50," was prepared for the proposed amendments, and it provides 5
the regulatory basis for this guide and examines the costs and benefits of the 6
rule as implemented by the guide. A copy of the draft regulatory analysis is 7
available for inspection and copying for a fee at the NRC Public Document 8
Room, 2120 L Street NW. (Lower Level), Washington, DC, as Enclosure 2 to 9
Secy 94-194.
i UNITED STATi2S NUCLEAR REGULATORY COMMISSION FIRST CLASS Mall POSTAGE AND FEES PAID WASHINGTON, D.C. 20555-0001 USNRC PERMIT NO. G-67 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300 9
i O
RA-1
AD9 3 -1 i'p R.-
u.g'o, U.S. NUCLEAR REGULATORY COMMISSION February 1995
' [,T 0FFICE OF NUCLEAR REGULATORY RESEARCH Division 1 n
C/
i I
Task DG-1035
/
t DRAFT REGULATORY GUIDE
Contact:
R.M. Kenneally (301)415-6303 1
DRAFT REGULATORY GUIDE DG-1035 2
(Previously Issued as Draft DG-1018) 3 RESTART OF A NUCLEAR POWER PLANT 4
SHUT DOWN BY A SEISMIC EVENT l
5 A.
INTRODUCTION j
6 Paragraph IV(a)(3) of Proposed Appendix S, " Earthquake E g C iteria for 4
7 Nuclear Power Plants," to 10 CFR Part 50, " Domestic Licens o
ion and 8 Utilization Facilities," would require shutdown of the nu plant if vibratory 9 ground motion exceeding that of the operating basis round motion (0BE) 10 occurs or if significant plant damage occurs.' P ming operations, the j
11 licensee must demonstrate to the NRC that no mage has occurred to those 12 features necessary for continued operation wi e risk to the health and safety Os 13 of the public, 14 This guide is being developed v
idance acceptable to the NRC staff for 15 performing inspections and tests of cl power plant equipment and structures prior 16 to restart of a plant that ha wn by a seismic event.
17 Regulatory guides are i ed describe and make available to the public such 18 information as methods accepta the NRC staff for implementing specific parts of 19 the Commission's re ulations, techniques used by the staff in evaluating specific 20 problems or postu cidents, and guidance to applicants. Regulatory guides are 21 not substitutes _fo ions, and compliance with regulatory guides is not required.
i I
22 being developed in Draft Regulatory Guide DG-1034, " Pre-23 Eart Planning and Immed' ate Nuclear Power Plant Operator Postearthquake 24 Action to provide criteria for plant shutdown.
j This regulatory guide is being issued in draft form to involve the public in the early stages of the development of a regulatory position in this j
area. It has not received complete staff review ar.d does not represent an official NRC staff poeirion, j
Public comments are being solicited on the draft guide (including any implementation schedule) and its associated regulatory analysis or valuehmpact statement. Comments should be accompanied by appropriate supporting data. Written comments may be submitted to the Rulee i
i Review and Directives Branch, DFIPS, Office of Administration, U.S. Nuclear Hagulatory Commission, Washington, DC 20555. Copies of comments received may be examined at the NRC Pubhc Document Room,2120 L Street NW., Washington, DC. Comments will be most helpful if r.ceived by May 12, 1995.
Requests for single copies of draft guides (which may be reproduced) or for placement on an automatic distribution list for single copies of j
future guides in specific divisions should be made in writing to the U.S. Nuclear Regulatory Commission, Washington, DC 20555, Attention:
Office of Administration, Distribution and Mail Services Section.
_h0 O M
1 Regulatory guides are issued in draft form for public comment to involve the
{
2 public in the early stages of developing the regulatory positions.
Draft 3
regulatory guides have not received complete staff review and do not represent 4
official NRC staff positions.
5 Any information collection activities mentioned in this draft regulatory 6
guide are contained as requirements in the proposed amendments to 10 CFR Part 7
50 that would provide the regulatory basis for this guide.
The proposed 8
amendments have been submitted to the Office of Management and Budget for 9
clearance that may be appropriate under the Paperwork Reduction Act. Such 10 clearance, if obtained, would also apply to any information collection 11 activities mentioned in this guide.
12 B.
DISCUSSION 13 Data from seismic instrumentation
- and a walkdown of the nuclear power 14 plant are used to make the initial determination of whether the plant must be 15 shut down after an earthquake, if the plant has not already shut down from j
16 operational perturbations resulting from the seism'ic event.'
17 The Electric Power Research Institute has developed guidelines that will 18 enable licensees to quickly identify and assess earthquake effects on nuclear 19 power plants in EPRI NP-6695, " Guidelines for Nuclear Plant Response to an 20 Earthquake,"' December 1989.
This regulatory guide addresses sections of 21 EPRI NP-6695 that relate to postshutdown inspection and tests, inspection 22 criteria, inspection personnel, documentation, and long-term evaluations.
23 EPRI NP-6695 has been supplemented to add inspections and tests as a 24 basis for acceptance of stresses in excess of Service Level C and to recommend 25 that engineering evaluations of components with calculated stresses in excess 26 of service Level D focus on areas of high stress and include fatigue analyses.
27 Holders of an operating license or construction permit issued prior to 28 the implementation date to be specified in the active guide may voluntarily 29 implement the methods to be described in the active guide and the methods 30
' Guidance is being developed in Draft Regulatory Guide DG-1033, the third j
31 Proposed Revision 2 to Regulatory Guide 1.12, " Nuclear Power Plant 1
32 Instrumentation for Earthquakes," that will describe seismic instrumentation i
33 acceptable to the NRC staff.
1 I
9l 34
'EPRI reports may be obtained from the Electric Power Research Institute, l
35 Research Reports Center, P.O. Box 50490, Palo Alto, CA 94303.
2
1 being developed in Draft Regulatory Guides DG-1033, " Nuclear Power Plant 02 Instrumentation for Earthquakes," and DG-1034, " Pre-Earthquake Planning and 3
Immediate Nuclear Power Plant Operator Postearthquake Action."
4 C.
REGULATORY POSITIOR 5
After a plant has been shut down by an earthquake, the guidelines for 6
inspections and tests of nuclear power plant equipment and structures that are 7
depicted in EPRI NP-6695 in Figure 3-2 and specified in Sections 5.3.2 8
(including Tables 2-1, 2-2, and 5-1), 5.3.3 (includes Table 5-1), and 5.3.4; 9
the documentation to be submitted to the NRC specified in Section in 5.3.5; 10 and the long-term evaluations that are specified in Section 6.3 (all sections 11 and subsections), with the exceptions specified below, would be acceptable to 12 the NRC staff for satisfying the requirements proposed in Paragraph IV(a)(3) 13 of the Proposed Appendix S to 10 CFR Part 50.
14 1.
EXCEPTIONS TO SECTION 6.3.4.1 0F EPRI NP-6695 15 M
Item (1) should read:
16 If the calculated stresses from the actual seismic loading conditions 17 are less than the allowables for emergency conditions (e.g., ASME Code 18 Level C Service Limits or equivalent) or original design bases, the item 19 is considered acceptable, provided the results of inspections and tests 20 (Section 5.3.2) show no damage.
21 M The second dashed statement of Item (3) should read:
22
-- An engineering evaluation of the effects of the calculated stresses 23 on the functionality of the item. This evaluation should address all 24 locations where stresses exceed faulted allowables and should include 25 fatigue analysis.
26 M
The last paragraph should read:
27 Reanalysis of safety-related piping systems is not considered necessary 28 unless there is observed damage to the piping systems.
Experience has 29 shown that piping systems designed to the ASME Code are not damaged by 30 inertia loads resulting from an earthquake.
If damage occurs, it will 31 most likely occur in the piping supports or as damage to the pipe at 3
l
1 fixed supports caused by relative support displacements. These types of 2
damage would be detected by the plant walkdown inspections and post-3 shutdown inspections described in Sections 4 and 5 of this report.
In 4
general, piping reanalysis should be performed on a sampling basis to 5
verify the adequacy of piping and to assess the need for supplemental 6
nondestructive examination of potential high-strain areas.
7 2.
LONG-TERM EVALUATIONS 8
Coincident with the long-term evaluations, the plant should be restored 9
to its current licensing basis.
Exceptions to this must be approved by the 10 Director, Office of Nuclear Reactor Regulation.
11 D.
IMPLEMENTATION 12 The purpose of this section is to provide guidance to applicants and 13 licensees regarding the NRC staff's plans for using this regulatory guide.
14 This draft guide has boen released to encourage public participation in 15 its development. Except in those cases in which the applicant proposes an 16 acceptable alternative method for complying with the specified portions of the 17 Commission's regulations, the method to be described in the active guide 18 reflecting public comments will be used in the evaluation of applications for 19 construction permits, operating licenses, combined licenses, or design 20 certification submitted after the implementation date to be specified in the 21 active guide. This guide would nct be used in the evaluation of an 21 application for an operating license submitted after the implementation date 23 to be specified in the active guide if the construction permit was issued 24 prior to that date.
4
1 REGULATORY ANALYSIS 2
A separate regulatory analysis was not prepared for this regulatory
-3 guide. The draft regulatory analysis, " Proposed Revision of 10 CFR Part 100 4
and 10 CFR Part 50," was prepared for the proposed amendments, and it provides 5
.the regulatory basis for this guide and examines the costs and benefits of the 6
rule as implemented by the guide. A copy of the draft regulatory analysis is 7
available for inspection and copying for a fee at the NRC Public Document 8_
Room, 2120 L Street NW. (Lower Level), Washington, DC, as Secy 94-194.
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