ML20039A650
| ML20039A650 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 12/01/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | Carty M COWLITZ COUNTY, WA |
| References | |
| TAC-47337, NUDOCS 8112210048 | |
| Download: ML20039A650 (35) | |
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DEC 011381 Docket No. 50-344 9'
D,
. 4' Mr. l1artin Certy, Director D
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. _- t nepartment of Cormnity Development t
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Coulitz County
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207 Fourth Avenue North U
W Velso, Washinoton 98626
Dear Hr. Carty:
kQ This is in response to your letter of October 29, 1031 wherein you asked questions renarding the proposed coal transshiprent facility to be located on property owned by the Port of Kala >ia and its relationship to tSe Trojan f:uclear Plant located across the Colmhia River.
In response to your question about the definition of " exclusion area", we have enclosed a copy of 10 CFP. Part 100 of MEC regulations. The defini-tion is presented in paragraph 100.3, " Definitions".
PGE, as operator of Trojan, is not required to own the entire excl.;sion area in order to exercise the control called for in the definition. The exclusion area for Trojan is traversed by Gregon State liighway 30, the Burlington !!crthern Railroad, and the Columbia River, arong others.
Agreements have baen nade for control of all activities within these areas. Copies of these agreements are enclosed for your inforration.
As to the effect of the exclusion area on the County's processing of the Port of Malama permit application, we are unfamiliar with your criteria or required findincs in order to issue such a pernit, so we are unable to provide a complete answer. f!evertreless, within the exclusion area itself, pCE would be required to demonstrate adequate control to satisfy the requirenents of 10 CFR 100.3(a).
Un have accepted the enclosed acree-ments for other activities as deconstratinq adequatt control for such activities. An appropriate agreccent would be needed for that portion of the coel transshipment facility that lies within the Trojan exclusion area.
teyond the exclusion area, protective actions in the event of a radio-logical enerqency at Trojan are under the jurie, diction of Cowlitz County (Onnartrent of Emercency Services) and tbc State of Fashinqton. Agreements related to emergency plannino have also been made between PGE and the above novernmental bodies and are also enclosed.
8112210048 811201 PDR ADOCK 05000344 H
PDR OFFICE) sunswe) oncy OFFICIAL RECORD COPY usoe e-mm ync ronu ata m em sncu em
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Emergency planning review responsibility outside the exclusion brea rests with the Federal Energency.Hanagement Agency (FEMA). To obtain more infor-mation directly from FEttA, contact:
ffr. W.11. Meyer, Director Region X Federal Emergency Management Agency 4
Federal Regional Center Bothell, Washington 98011 l
Telephone:
(206) 481-8800 l
A copy of your letter and this response is being sent to FEttA Region X for j
their information.
J
' You may also wish to contact the Cowlitz County Departnent of Energency Services for further energency planning information.
In conclusion, based on the nature of the proposed project as we understand it today, we have no basis for believing at this tine that the operation of a coal transshipnent facility at the proposed location opposite the Trejan fluclear Plant would pose a significant hazard to the public health and safety provided that PGE arranges for appropriate control of activities at the coal facility within their exclusion area boundary, and provided that the energency plans appropriately consider and account for the coal transshiprent facility and activities associated with it.
4 I
The !!RC project canager for Trojan is Charles Tranmell ((301) 492-7389).
Picase feel free to contact him should you need other information or assistance.
4 i
l Sincerely, Odginst signc'J b.y Robert A. Clark Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensinq i
Enclosures:
1.
Letters of Agreement cc w/ enclosures and incoming:
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See next pace n
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7 J ' *see previous d r concurrence and distribution.
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, Energency planning review responsibility outside the exclusion area rests with FEMA. You may wish to contact them directly for more information:
Mr. W. H. I! eyer, Director Region X Federal Emergency Management Agency Federal Regional Center Bothell, Washington 98011 Telephone:
(206) 481-8800 A copy of your letter and this response is being sent to FEMA Region X for their information.
+
You may also wish to contact the Cowlitz County Department of Emergency Services for further emergency planning information.
s In conclusion, based on the nature of the proposed project as we understand it today, we believe that the operation of a coal transshipment facility at the proposed location opposite the Trojan Nuclear Plant would pose no significant hazard to the public health and safety provided that PGE arranges for appropriate control of activities at the coal facility within their exclusion area boundary, and provided that the energency plans appropriately consider the naw installation and associated activity.
The !!RC p?oject manager for Trojan is Charles Trarre11 ((301) 492-7389).
Please feel free to contact him should you need other infornation or assistance.
Sincerely, f
Robert A. Clark, Chief Operating Reactors Branch f3 Division of Licensing l
Enclosures:
DISTRIBUTION:
1.
- Docket File JHeltemes FPagano 2.
Letters of Agreenent NRC'POR PMKreutzer-3 g, M m.
L PDR CTrarmlell cc w/enclosiees NSIC RAClark b 'D "M >
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[puttnq[o, UNITED STATES NUCLEAR REGULAJORY COMMISSION 5
E WASHINGTON, D. C. 20555 k
DEC 0 1 1981 Docket No. 50-344 Mr. Martin Carty, Director Department of Community Development Cowlitz County 207 Fourth Avenue North Kelso, Washington 98626
Dear Mr. Carty:
This is in response to your letter of October 29, 1981 wherein you asked questions regarding the proposed coal transshipment facility to be located on property owned by the Port of Kalama and its relationship to the Trojan Nuclear Plant located across the Columbia River.
In response to your question about the definition of " exclusion area", we The defini-have enclosed a copy of 10 CFR Part 100 of NRC regulations.
tion is presented in paragraph 100.3, " Definitions".
PGE, as operator of Trojan, is not required to own the entire exclusion area in order to exercise the control called for in the definition. The exclusion area for Trojan is traversed by Gregon State Highway 30, the Burlington Northern Railroad, and the Columbia River, among others.
Agreements have been made for control of all activities within these Copies of these agreements are enclosed for your infomation.
areas.
As to the effect of the exclusion area on the County's processing of the Port of Kalama permit application, we are unfamiliar with your criteria or required findings in order to issue such a pemit, so we are unable to provide a complete answer. Nevertheless, within the exclusion area itself, PGE would be required to demonstrate adequate control to satisfy the requirements of 10 CFR 100.3(a). We have accepted the enclosed agree-ments for other activities as demonstrating adequate control for such activities. An appropriate agreement would be needed for that portion of the coal transshipment facility that lies within the Trojan exclusion area.
Beyond the exclusion area, protective actions in the event of a radio-logical emergency at Trojan are under the jurisdiction of Cowlitz County (Department of Emergency Services) and the State of Washington. Agreements related to emergency planning have also been made between PGE and the above governmental bodies and are also enclosed.
/
l 6ww
/ Emergency planning review responsibility outside the exclusion area rests with the Federal Emergency Management Agency (FEMA). To obtain more infor-mation directly from FEMA, contact:
Mr. W. H. Meyer, Director Region X Federal Emergency Management Agency Federal Regional Center Bothell, Washington 98011 j
Telephone:
(206) 481-8800 A copy of your letter and this response is being sent to FEMA Region X for their infomation.
You may also wish to contact the C0w11tz County Department of Emergency Services for further emergency planning infomation.
In conclusion, based on the nature of the proposed project as we understand it today, we have no basis for believing at this time that the operation of a coal transshipment facility at the proposed location opposite the Trojan Nuclear Plant would pose a significant hazard to the public health and safety provided that PGE arranges for appropriate control of activities at the coal facility within their exclusion area boundary, and provided that the emergency plans appropriately consider and account for the coal transshipment facility and activities associated with it.
~
The NRC project manager for Trojan is Charles Trammell ((301) 492-7389).
Please feel free to contact him should you need other information or assistance.
Sincerely, I
Gc Robert A. Clark, Chief Operating Reactors Branch #3
- j Division of Licensing
Enclosures:
1.
2.
Letters of Agreement cc w/ enclosures and incoming:
See next page
)
(
r Portland General Electric Company cc: Multnomah County Library Social Science and Science Department 801 S.W. 10th Avenue Portland, Oregon 97205 Michael Malmros, Resident Inspector U. S. Nuclear Regulatory Commission Trojan Nuclear Plant P. O. Box 0 Rainier, Oregon 97048 i
Robert M. Hunt, Chairman Board of County Commissioners 4
Columbia County St. Helens, Oregon 97501 i
Donald W. Godard, Supervisor Siting and Regulation Oregon Department of Energy j'
Labor and Industries Building Room 111 Salem, Oegon 97310 Mr. W. H. Meyer FEMA X I
Bothell, Washington 98011 Department of Emergency Services Cowlitz County Kelso, Washington 98625
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9 k
'l UNITED STATES NUCLEAR REGULATORY COMMISSION RULES and REGULATIONS
, Q TITLE 10. CHAPTER 1. CODE OF FEDERAL REGUI.ATIONS-ENERGY PART REACTOR SITE CRITERIA 100 i
4 8
- *", i Q 100.2 Scope.
provided that no significant haza*ds to oo p,,,,,,
the public health and safety will result.
' 100.2 Scope.
(a) This part applies ta applications (b) 1.ow population zone means the IW Dennitions.
filed under Part 50 of this chapter for area immediately surrounding the exclu-SITE EVALtJATION FACTORS stationary power and testing reactors.
sion area which contains residents, the (b) The site ent:ria contained in this total numt>er and density of which are 100.30 Factors to be considered when evalu.
part apply primarily to reactors of a such tl.at there is a reasonable probability suns snes.
general type and design on which ex-that appropriate protective measures 100.11 Determination of esclus6on ares, low per ence has been developed, but can could be taken in their behalf in the event population zone. and population center distance.
also be applied to other reactor types.In g
particular, for reactors that are novel in spech a permissible population density APPENDIX A - Seismic and Geoloste Siting design and unproven as prototypes or or total population within this zone Crtteria for Nuclear Power Plants pilot plants,it is expected that these basic because the situation may vary from case entena will be applied in a manner that to case. Whether a specific number of C
takes into account the lack of expenence.
people can, for example, be evacuated In the application of these criteria fr m a specific area, orinstructed to take which are deliberately fler.ible, the shelter, n a timely basis will depend on AUTHORITY: Secs. 202, ISab. L.93-438, safeguards provided-either site isolation many factors such as location, number 88 Stat.1244 (42 U.S.C. 5842) or engineered features-should reflect the and size of highways, scope tr d extent of Q 100.1 Purpose.
lack of certainty that only experience ce advance planning, and actual distnbution (a) It is the purpose of this part to: E'
- of residents within the area.
desenbe entens which guide the Com 100.3 Definitions.
2 (c) " Population center distance" mission in its evaluation of the suitabilityI f means the distance from the reactor to As used in this part:
nearest boundary of a densely of proposed sites for stationary power; (a) " Exclusion area" means that area; the i
and testing reactors subject to Part 50 of surrounding the reactor, in which the populated center containing more than about :5,000 residents.
this chapter.
reactor licensee has the authority to i
(b) Insufficient experience has been determine all activities including exclu-(d) " Power reactor" tr.eans a nuclear on or removal of personnel and reactor of a type described in { 50.21(b) accumulated to permit the writing of or 50.22 of this chapter desisned to
- detailed standards that would provide a property from the area. This area may be produce electrical or heat energy.
quantitative correlation of all factors traversed by a highway, railroad, or i
g significant to the question of accepta*
waterway, provided these are not to close (e) " Testing reactor" means a " testing
- bility of reactor sites. This partisintended to the facility as to interfere wit.. normal facility" as defined in Q 50.2 of this as an interim guide to identify a number operations of the facility and provided chapter.
of factors considered by the Commission appropriate and effective arrangements SITE EVALUATION FACTORS m the evaluation of reactor sites and the are made to control traffic on the general enteria uwd at this time as guides highway, railroad, or waterway,in case of Q 100.10 Factors to be considered when in approving or disapproving proposed emergency, to protect ti r c:blic health evaluating sites, sites. Any applicant who believes that and safety. Residence v Se exc!u-Factor? considered in the evaluation of factors other than those set forth in the sion area shall normally
.ted. In sites include those relating both to the guide should be considered by the Com-any event, residents sh-et to proposed reactor design and the charac-mission will be expected to demonstrate ready removal in cas
't.
tenstics peculiar to the site. It is expect 6d l
l the applicability and significance of such Activities unrelated to c
- hat reactors will ref;ect through their g
factors. '
reactor may be permitted.
~r,n, constniction and operation an li V
area under appropnate "ly low probability for accidents l
100-1 August 1,1980
m o
t 1
PART 100 e REACTOR SITE CRITERIA
~
that could result in release of significant have a bearing on the consequences of an (3) A population center distance of at s
quantities of radioactive fission produrts.
escape of radioactive material from the least one and one-third times the distance in addition, the site location and the facility. Special precautions should be from the rea; tor to the outer boundary engineered features included as safeguards planned if a reactor is to be located at a. of the low population zone. In applying against the hazardous consequences of an site where a significant quantity of radio
- this guide, the boundary of the popula-accident, should one occur, should insure active sffluent might accidentally flow
- tion center shall be determined upon a low risk of public expo *ure. In particu-into nearby streams or rivers or might f consideration of population distribution, lar, the Commission will take the find ready access to underground water: Political boundaries are not controllingin following factors into :onsideration it; tables.
the application of this guide. Where very determining the acceptability of a site for (d) Where unfavorable physical char-large cities are involved, a greater distance a power or testing reactor:
acteristics of the site exist, the proposed may be necessary because of total (a) Characteristics of reactor design site may nevertheless be found to be integrated population dose consideratMn.
and proposed operation includmg:
acceptable if the design of the facility (1) Intended use of the reactor includes a ppropriate and adequate (b) For sites for multiple tsotor including the propowd maximum power compensating engineering safeguards.
facilities consideration should be given to the following; level and the nature and inventory of 9 100.11 Determination of exclusion (1) If the reactors are mdependent to contained radioactive materials; area, low population tone, and popu.
the extent that an accident in one reactor 2
(2) The extent to which generally lation center distance.
would not initiate an accident in another,
[ accepted engineering standards are (a) As an aid in evaluating a proposed the size of the exclusion area, low popula-
- applied to the design of the reactor; site, an applicant should assume a fission tion zone and population center distance (3) The extent to which the reactor 3
produce release freim the core, the shall be fulfilled with respect to each incorporates unique or unusual features having a significant bearing on the expected demonstrable leak rate from the reactor individually. The envelopes of the and the meteorological plan overlay of the areas so calculated probability or consequences of accidental, containment conditions pertinent to his site to derive shal then be taken as their respective release of radioactive materials; (4) The safety features that are to be; an exclusion area, a low population zone. boundaries.
engineered into the facility and those[ and population center distance. For the:
(2) If the reactors are interconnected barriers that must be breached as a result
- purpose of this analysis, which shall set; to the extent that an accident in one of an accident before a release of radio.
forth the basis for the numerical valuesI reactor could affect the safety of opera-used, the applicant should determine thea tion of any other, the size of the exclu-active material to the environment can followmg:
sion area, low population zone and occur.
(b) Population density and use charac.
(1) An exclusion area of such size that population center distance shall be based teristics of the site environs, including the an individual located at any point on its upon the assumption that all inter-exclusion area, low population zone, and boundary for two hours immediately connected reactors emit their postulated population center distance.
following onset of the postulated fission fission product releases simultaneously.
(c) Physical characteristics of the site, product release would not receive a total This requirement may be reduced in including seismology, meteorology, radiation dose to the w!T e body in relation to the degree of coupling i
8 excess of 25 rem or a total radiation between reactors, the probability of geology and hydrology, t
dose in excess of 300 rem to the thyroid concomitant accidents and the proba-(1) A p pe n dix A,
" Seismic and from iodine exposure.
bility that an individual would not be Geolcsic Siting Criteria for Nuclear (2) A low population zone of such exposed to the radiation effects from Power Plants," describes the nature of size that an individual located at any simultaneous releases. The applicant investigations required to obtain the pomt on its outer boundary who is would be expected to justify to the geologic snd seismic data necessary to exposed to the radioactive cioud resulting determine site suitability and to provide from the postulated fission product
- reasontble assurance that a nuclear power release (during the entire period of its ey aw or 25 nm refure y plant can be constructed and operated at passage) would not receive a total radia-j, e[ ole p
z a proposed site without undue risk to the tion dose to the whole body in excess of hfetne occ6 dental or emersency dow for radia-l 1 health and safety of the public. It 25 tem or a total radiation dose m excess tion workers which, accordms to NCRP
" describes procedures for determinind the of 300 rem to the thyroid from todme recommendations may be disresarded in the cetermmation of their radiation esposure status design basis at a site due to earthquakes
-ex posure.
quantitative vibratory ground motion (we NBS Handbook 49 dated June s.19s9).
However, neither its use nor that of the 300 and describes information needed to rem value for thyroid esposure as set forth in determine whether and to what extent a
!The fission product reiesse
-
- for thew site criteria svides are intended to imply these calculations should be based that these nurnbere constitute acceptable limits nuclear power plant need be designed to accident. hyPothesind for purr
'd emergency doses to the public under acci-
_ ithstand the effects of surface faultsg. analysis or postulated from con t conditions. Rather, this 2s tem whole w
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I (2) Meteorolo05 cal conditions at the potential hasards not escoeded t forth in these guides es reference
- site and in the surrounding area should be any accident considered credib?
' can be used in ime evaluaison or z considered.
dents han senerany been assume
.tg nspect to potential reactor
[
(3) Geological and hydrological substantist rneltdown of the co" codinsry to probability of g
'*4""' " ' ' * * * * ' ' " " * ' * " ' ' " "
"l characteristics of the proposed site may fleston products.
August 1, W 100-2
PART 100 e REACTOR SITE CRITERIA 111. DEFINITIONS
[
satisfaction of the Commission the basis ~ APPENDIX A.-SEISMIC AND GEOLOGIC ti for such a reduction in the source term.
SITING CRITERIA FOR NUCLEAR As umed in these criterie:
POWER PLANTS (a) The " magnitude of an earthquake la a I
(3) The applicant is expected to show
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that the simultaneous operation of I. PURPOSE related to the energy released in the form of mult:ple reactors at a site will not result General Design Cri*erion 2 of Appendia A seismic waves. "Mesnatude" mesna the numeri-in total radioactive effluent releases to Part $0 of this chapter requires that nuclear cal value on a Richter scale.
beyond the allowable limits of applicable pown plant structurn, systenis. and cm (b) De " intensity" of en unhquake is a ponenta important to safety b* swied to measure of its effects on man, on man. built regulations, withstand the effects cf natural U.assomena structures, and on the earth's surface at a Note: For further guidance in such as es,thq ua kes, tornadoes, hurricanes, particular location. "Intensit y" means the developing the exclusion area, the low noods, tsunami. and seiches without loss of numerical value on the Modined Mercaniscale.
zone, and the population capability to perform their safety furictions. It (c) Tb " Safe Shutdown Earthquake"'
is
% population is the purpose of these criteria to set forth tha that ee6euske which is based upon an evalus-center distance, reference is made to a
principal seismic and geologic considerations thr. of the manimum earthquake potentist l.
l Technicalinformation Document 14844*
which guide the Commission in its evaluatio" of considering the regional and local seology and
- dated March 23, 1962, which contains a the suitsbuity of proposed sites for nuclear seismology and specific characteristics of local procedural method and a sample calcula.
power plants and the suitsbility of the plant subsurface material. It is that earthouake which tion that result in distances roughly design bases established in consideration of the produces the manimum vibratory ground seismic and geologic characteristics of the motion for which certain structures. systems, reflecting current siting practices Cf the 7,,pos,d sites, and components are designed to remain func.
[
Comminion. The calculations desenbed These criteria are based on the limited tionst. These structures systems. and com.
in Technical Information Document geophysical and geological information availa-pocents are those necessary to easure:
r4844 may be used as a point of de.
bla to date concerning raults and es-thquake (t) The integrity of the rescior coolant occurnau and eMect. Dey will be nvised as pressure boundary.
IFJture for consideration of particular when rocre complete Information (2) The capability to shut down the reactor site requirements which may result from
- necessary becomes avadable.
and maintain it in a safe shutd2wn condition, evaluation of the characteristics of a ll. SCOPE particular reactor, its purpose and (3) The capabdity to prevent or mitigste DeH crHena. whd PNy M nuclear p?*"
the consequences of accidents which coind
. method of operation' plants, describe the nature of the investigations result in potennal offsite exposures comparable required to obtain the geologic an4 seismic data to the guideline exposures of this part.
Co pies of Technical Information necessary to determme site suitabdity and (di The " Operating Basas Earthquake" is Document 14844 may be obtamed from
- provide reasonable assurance that a nuclear that eaeisquake which,considering the regional I the Commission's Public Document 3 power plant can be constructed and operated at h and total geology and seismology and specific
- P' P "d
'"' *"h
""d" "8N Room,1717 H Street NW., Washington, health and safety of the public.'They describe 6I 's characteristics of local subsurface material.
could reasonably be espected to affect the g
.u D.C..
or by writing the Director ofg procedures for determinwg the quantitattve : pi,t site durvig the operstirig life of the plant;
% Nuclear Reactor Regulatiort U.S. Nuclear v6bratory ground motion design basis at a site it is that earthquake which produces the Re gulatory Commission, Washington, due to earthquakes and describe informatio" vibratory growth mo tion for which those
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I""'"h'""P'*"P'"'"'**'Y entent a nuclear power plant need be designed for contmued operation without undue risk to to withstand the effects of surface faulting.
the health and safety of the public are designed Other geologic and eeismic factors requked to to remain functionsi.
be taken into account in the alting and design (e) A " fault" is a tectonic structure along of nuclear power plants are identified.
which differential slippage of the adiacent earth The in ve st igations described in this materials has occurred parallel to the fracture appendia are within the scope of Investigations plane.18 s distinct from other types of ground permitted by l 50.10(c)(1) of this chapter.
disruptions such as landslides, fissures, and Each applicant for a construction permit craters. A fault may have souge or breccia shall investigste all seismic and geologic factors between its two walls and includes any sesoci-that may affect the design and operation of the sted monoclins!flexureor other similar geologic proposed nuciear power plant irrespective of structural feature, whether such factors are esplicitly included in (f) " Surface faulting" is differential ground I
these criteria. Additional investigations and/or displacement at or near the surface caused I
more conservative determinations than those directly by fault movement and is distinct from
{
included in these criteria may be required for nontectonic types of ground disruptions, such sites located in areas having complex geology or
,, g, slides, fissures, and craters.
1 in areas of high seismicity, if an applicant
(
\\ " capable fault" is a fault which has believes that the particular seismology and ethion.J one or more of the following charse.
geology of a rite indicate that some of these teristics:
critetta, or portions thereof, need rior be f t) Movement at or near the ground surface satisfied, the specific sections of these criteria at le?st once within the past 3s 00o years or should be identified in the license application.
movemest of a recurnns nature within the past and supporting date to justify clearly sbch
$00.000 ya era.
departures should be presented.
(2) M s.ro.se is micit y in st r u m e n tally These criteria do not address investtfstions determmed 'with records of suffielent precision of volcanic phenomena requireJ for site s to demonsti ste a direct relationship with the located in areas of volcanic ac.
- v. Investiga.
g,,gg, tions af the volcsaic aspects
-* sites will be determined on a case.by.cs.
i
' The " Safe Shutdoe Earthquake" defines rethquake which has commonly been i
- as the " Design Basis Estthquake."
f I
August 1,1980 l
j
I 1
PART 100 o REACTOR SITE CRITERIA (3) A structural relationship to a capable (a) Arquired invert (gerion for Vibra tory tectonic provinces any part of which is located i
fault according to characteristics (l) or (2) of Ground Morton. The purpose of the investiga.
within 200 mues of the site; y/
tions required by this paragraph la to obtain (7) For favita, any part of which is within I
this paragraph auch that movement on one Information needed to describe the vibratory 200 mues' of the site and which may be of
'I could be reasonably espected to be ac.
companied by movement on the other.
ground motion produced by the Safe Shutdown significance in establish >g the Safe Shutdown la wmo cease, the geologic evidence of past Earthqaske. All of the steps in paragrapha Earthquake, determination of whether these actkNfy at or near the ground surface along a (t)(3) through (a)(g) of this section need eat be faults are to be considered as capeMe faults.8
particular fault may be obscured at a particular carried out if the Safe Shutdown Eerthquake This determination la required an order to see. Thas might occur, for example, at a site can be clearly established by investigations and permit appropume consideration of the geo-P aving a deep overburden. For these cases, determmettons of a lesser scope. The investiga-lovc history of abh fautta in establishing the evidence may exist elsewhere along the fault tions required by this paragraph provide an S.fe Shutdown Earthquake. For guidance in from which an evaluation of its characteristics adequate baats for selection of an Operating determining which faults may be of significence bt the vicintly of the alte can be reasonably Basia Earthquake. The investisations shan in determining the Safe Shutdown Earthouske.
based. Such eviJence shou be used in determin.
include the fouowing:
Ttble I of this appendit presents Jea minimum ing whether the fault la a capable fault within (1) Determination of the uthologic, strat-length of fault to be cm aldered versus diettace d
this definition.
igraphic. hydrologic, and structural geologic from site. Capable fauga of lesser length Otan f
Notwithstanding the foregoing paragrapha conditions of the site and the region sur-those indicatod in Tab!91 and feulta wnich ste I11(3)(1). (2) and (3), structural association of a rounding the site, including its geologic history; not ;epeble faulta neaJ not be considered in fault with geologic structural features which are (2) Identification and evaluation of tectonic determining the Safa Shutdown Earthquake, geologicauy' old (at least pre-Quaternary) such structures underlying the alte and the region except where unusual circumsee.cas indicate as many of those found in the Eastern region of surrounding the site, whether buried or such consideration la appropriatal the United States shau, in the ebeence of empressed at the surface. The evaluation should g
Table I conflicting evidence. demonstrate that the fault consider the possible effects caused by taan's is not a capable fault within this definit 6on.
activities such na withdrawal of fluid from or Minimum (h) A " tectonic province" is a region of the addition of fluid to the subsurface, entraction Distance from the site (mues):
lengthd Nort's American continent cherecterland by a of minerals, or the loading effects of dams or 0 to 20.
I relative consistency of the geologic structural reservoirs; j
Greater than 20 to 50.
features contained there n.
(3) Evaluation of physical evidence %
Greater than $0 to 100
. 10 20 (1) A " tectonic structure" is a large scale concerning the behavior during prior earth'*
Greater than 100 to !$0..
dislocation or distortion within the earth's quakes of the surficsel geologic motorials and[
Greater than 150 to 200......
., 40 crust. Its eatent le messured in mues.
the substrata underlying the site from the.
Q) A " tone requiring detailed faulting Uthologic. atratigraphic. and structorsi geologic" eMinimum length of fazit (maes) which shnu be considered in establishing Safe Shut-investigation" is a tone within whkh a nuclear studies; power reactor may not be located unleen a (4) Determination of the static and down Earthquake.
detailed investigation of the regional and local dynamic engineering properties of the matertsia
, geologic and seiamt: characteristics of the site, underlying the site. Included should he proper.
(3) For capable faults. any part of which la Z demonstrates that the need to design for; ties needed to determine the behaviot of the within 200 mGes' of the site and which may be
- surfaca faulting has been properly determined.; underlying material during earthquakes and the of significance in establishing the Safe Shut.
V (k) The " control width" of a fault is ther characteristics ut the underlying material in down Earthquake, determination of:
s"' monimum wida of the zone containing' transenitting earthquake. induced motions to the (1) The length of the fault; I mapped fe,lt traces, including au faults whichE foundations of the plant. such as setemic wave (ii) The relationship of the fault to regional can be reasonably inferred to have empertenced velocities, density water content. porealty, and tectonic structures; and differential movement during Quaternary strength; (lii) The nature, amount. and geologic times and which join or can reasonably be (5) Listing of au historically reported earth.
history of displacements along the fault, inferred to Join the main fault trace, measured quakes which have affected or which could
- ncbding particularly the estimated amount of within 10 mues along the fault's trend in both reasonably be espected to have affected the the maximum Quaternary displacement related directions from the point of nearest approach site, including the date of occurrence and the to any one earthquake along the fault.
to the site. (See Figure 1 of this appendix.)
following measured or estimated data:
(b) Requind Invesnterion for SurAce (1) A " response spectrum"is a plot of the magnitude or highess intensity, and a plot of Faultfar. The purpose of the investigations maximum responses (acceleration, velocity or the epicenter or location of highest intensity.
required by this paragraph is to obtain informs.
displacement) of a family of idealized single.
Where historicaUy reported earthquakes could tion to determine whether and to what extent degree-of-freedom damped oscillators assinst have caused a maximum ground acceleration of the nuclear power plant need be designed for natural frequencies (or perioda) of the oseg.
at least one-tenth the acceleration of gravity surface faulting. If the design basis for surface
[g lators to a specified vibratory motion input at (0. lg) at the foundations of the proposed faulting can be clearly established by investi.
nuclear power plant structures, the acceleration sations of a lesser scope, not an of the steps in thesr espports, r n ensity an uret on smund shaking at paragraphs (bM thmugh (b)(7)of this section IV, REQtJIRED INVESTIGATIONS these foundations shall also be estimated. Since need be carried out. The investigettons shall The geologic, setsmic and engineering char.
earthquakes have been reported in te*ms of include the following:
asteristics of a site and its environs than be various parameters tuch aa magnitude,intenalty
'If the Safe Shutdown Earthquake can be irrvestigated in sufficient scope and detail to at a stven location, and effect on ground.
sanociated with a fault closer than 200 miles to provide reasonable seaurence that they are structures, and people at a specific location, the site, the procedures of paragraphs (a)(7) sufficiently well understood to permit en some of these data may have to be estimated by and (s)(3) of this section heed not be carried odequate evaluation of the proposed site. and uas of appropriate empirical relationahlps. The out for successively more re-tote faults, to provide sufficient information to support the comparative characteristics of the material
'In the absence of absolute dating.ev6dence determinettone required by there criterte and to underlying the epicentrallocation or region of of reconey of rnovernent may be obtained by permit adequate engineering solutions to actual highest intensity and of the material undertvuts applying relative dating technique to ruptured, or potential geologic and solemic effects at the the site in transmitting earthquake vibratory O f f 8-
- erped or otherwise structurally proposed site. The sine of the region to be motion shan be considered; disturbed surface or near surface materials or investigated and the type of dets pertinent to (g) Correlation of epicenters or locations of geomorphic features.
the investigations shall be determined by the highest intenalty of historicauy reported earth,
'The applicant shall evaluate whether or not nature of the region surrounding the proposed quakes, waere possible, with tectonic structures a fault is a capable fault with respect to the atte. The lavestigations shall be carried out by a any part of which is located within 200 miles of characteristics outlined in paragrapha lll(g)(1),
ra 91 review of the pertinent literature and field the site. Epicenters or locations e (2 h and (3) by conducting a reasonable I
givestigations and shau include the steps antensity which cannot be reasonsb:.
in vestigation u sin g suitable geologic and v
h obtlined in paragraphs (a) through (c) of this with tectonic structures shall be ide, teOF ysacas techasques, h
sectson.
i August 1,1980 100 4
i r
PART 100 e REACTOR SITE CRITERIA (t) Determination of the lithologic, atrati-associated with historic tsunami in the same shau be determined in addition, for capable t
graphic. hydrologic, and structural geologic coastal region as the site shall also be included; fautta, the information required by persgraph V
conditions of the site and the aree surrounding (ii) Local features 2f coastal topography (aXs) of Section IV shall also be taken into e
the este, including its geologsc history; which might tend to modify tsunami runup or account kt determining the earthquakes of 8
(2) Evaluation of tectonic structures drawdown. Appropriate available evidence greatest magnitude related to the faults. The underlying the sate, whether buried or re g arding h ntoric local modifications in magnitude or intensity of earthquakes based on empressed at the surface, with regard to their tsunami runup or drawdown at coastal loca-geologic evidence may be larger then that of the potential for causens surface displacement at or tions having topography similar to that of the maximum earthquakes historicany recorded.
near the site. The evaluation shall consider the site shau also be obramed; and The accelerations at the site shall b3 determined possible effects caused by man's activities such (lii) Appropriate geologic and seismic assuming that the epicenters of the earthquakes as withdrawal of fluid from or addition of fluid evidence to provide information for establishing of greatest magnitude or the locations of to the subsurface, entraction of manerals, or the the design basis for seismically induced floods highest intensity related to the tectonic struc-losding effects of dams or reservoirs; or water waves from a local offshore earth-tures are situated at the point on the structures (3) Determination of geologic evidence of quake, from local offshore effects of an closest to the atte; fault offset et or near the ground surface at or onshore earthquake, or from coastal su b.
(11) Where epicenters orlocations of highest sidence. This evidence shall be determined, to intensity of historically reported earthquakes near the sate; (4) For fautta greater than 1000 feet long, the entent practical, by a procedure similar to cannot be reasonably related to tectonic struc.
j any part of which is within $ males' of the site, that required in paragraphs (a) and (b) of this fures but are identified pursuant to the require-determination of whether these faulta are to be section. The probable slip characteristics of ments of paragraph (s)(6) of Section IV with consadered as capable feutta.
offshore faulta shall also be considered as well tectonic provinces in which the site le located.
l (5) Listing ut all historicauy reported earth.
as the potential for offshore slides in s.abmarine the accolorations at the alte shau be determined ensuming that these earthquakes occur at the f
quakes which can reasonably be sesociated with material capable faulta gretter than 1000 feet long, any (2) For sites located near lakes and rivers.: site.
I
- part of which le within 5 mues' of ;he site, investigations simuar to those required in para-2 (111) Where epicenters or locations of the graph (c)(1) of this section shall be carried out." highest intensity of historically reported earth-g including the date of occurrence as:d the quakes cannut be reasonably related to tectonic a following measured or estimated data:
as appropriate, to determine the potential for w
% magnitude or highest intensity, and a plot of the nuclear power plant to be esposed to m structures but are ident! fled pursuant to the arismically induced floods and water waves es, requirements of paragraph (a)(6) of Section IV
[ the epicenter or reg 6cn of highest intensity; for example, from the failure during an earth-with tectonic provinces in which the este le not (6) Conelation of epicenters or locations of
- highest intensity of historically reported earth.
quake of an upstream dam or from slides of located, the accelerations at the site shau be quakes with capable faults greater than 1000 earth or debris into a nearby take.
determined assuming that the epicenters or locations of highest intenesty of these earth-feet long, any part of which is located within 5 V. SEISMIC AND GEOLOGIC quake
- are at the closest potnt to the site on the mGes' of the sate:
DESIGN BASES boundary of the tectonic province; (7) For capable faulte greater than 1000 8
(a) Determinarfon of Design Saar for (iv) The earthquake producing the feet long, any part of which is within 5 milea of the safe, determination of:
g Vibretory Ground Aforfon. The design of each maximum vibratory acceleration at the site, sa (t) The length of the fault; 3 nuclear power plant shall tske into account the determined from paragraph (a)(1)(i) through (ii) The relationship of the fault to regionala potential effects of vibratory ground motion (iii) of this section shall be designated the Safe tectonic structures:
[ cauard by earthquakes. The desagn basis for the Shutdown Earthquake for vibretory ground y
(iii) The nature, amount, and geologic, manimum vibratory ground motion and the motion, except as noted in peregraph (a)(1)(v) history of displacements along the fault.' etPected vibratory ground motion should be of this section. The characteristica of the Safe includsas particularly the estimated amount of determined through es slustion of the Shutdown Earthquake shall be dertved from the mesimum Quaternary displacement related erismology. geology, and the seismic and geo-more than one earthquake determined from to any one earthquake along the fault;and logic history of the site and the surrounding paragraph (a)(1)(1) through (lii) of this section.
(iv) The outer limits of the fault established region. The most severe earthquakes sesociated where necessary to ensure that the maalmum by mapping Quaternary fault tra:es for 10 with tectonic structures or tectonic provinces in vibratory acceleration at the site throughout miles along its trend in both directions from the the region surrounding the este should be the frequency range of interest la included. In point of its nearest approach to the site.
identified. considering those historically the case where a causative fault is near the site.
(c) Required Investrgstfon for Seasmically reported earthquakes that can be associated the effect of proximity of an earthquake on the Induced Floods and Water Ivows. (1) For with these structures or provinces and other spectral characteristics of the Safe Shutdown cuestal sstes. the investigations thallinclude the relevant factors. If faults in the region sur-Earthquake shnu be taken into occount.
de termination of:
rounding the site are capable faults, the most
~
t (i) Information resseding distantly and severe earthquakes associated with these faults The locady generated waves or tsunami which have should be determined by also considering their procedures in paragraphs (s)(1)(1) through affected or could have affected the site. Availa.
geologic history. The vibratory ground motion (a)(1)(lii) of thle section shall be applied in a g
ble evidence regarding the runup sad drawdown at the site should be then determined by co nservettve manner. The determinations assuming that the epicenters or locations of carried out in accordance wit h peregraphs highest intensity of the earthquakes are situated % (a)(1)(ii) and (a)(1)(lii) shad assure that the safe f
at the point on the tectonic structures ore shutdown earthquake intensity is, as a mini-
'If the design beans for surface faulting can tectonic provmces nearest to the sate. The 8 mum, equal to the maximum historic earth-be determined from a fault closer than 5 mdes earthquake which could cause the maximum b quake intensity experienced within the tectonic to the site, the procedures of paragraphs (b)(4) vibratory ground motion at the sate should be
- province in which the site is located. In the through (b)(7) of this section need not be designated the Safe Shutdown Earthquake. The event that geological and seismological dets carried out for soccessively more remote faults, specific procedures for determining the design warrant, the Safe Shutdown Earthquake shall In the absence of absolute dating. evidence basis for vibtstory ground motion are grven in he larger than that derived by use of the of recency of movement may be obtained by the following paragraphs.
procedures set forth in Section IV and V of the applying relative dating techniques to ruptured.
(t) Determmenon of Safe Shutdown Earth-Appendia.
of f set, warpeJ or otherwee structurally quate. The Safe Shutdown Earthquake shad be
=
disturbed surface of near-surface materials or identified through evaluation of seismic and l~
The maximum vibratory accelers.
geomorphic features-geologic information developed pursuant to theE tions of the Safe Shutdown Earthquake at each
'The applicant shall evaluate whether or not requirements of paragraph IV(a), as follows:
I of the wartous foundation locations of the (t) The historic earthquakes of greatest nuclear power plant structures et a given site magnitude ce intenesty which have been cor*[w shall be determined taking into a e fault la a capable fault with respect to the cherectoristics outlined in peregraphs 11!(g)(l).
f (2). and (3) by conducting a reasonable investi-related with tectonic structures pursuant to the
- characteristics of the underlying soll motertalin gation using auttable geologic and geophysical requirements of paragraph (a)(6) of Section IV l transmitting the earthquake-induced motions.
V techniques.
l 100-6 August 1.1980 I
k
1
~
t i
y PART 100 e REACTOR SITE CRITERIA obtained pursuant to paragraphs (aKI).(3),4nd TABLE 2 In evatusting the offshore effects of local earthquakes shall be determined by a procedure U
I (4) of section IV. The Safe Shutdown Earth.
8 similar to that used to determine the charac-5 quake shall be defined by response spectra
d'
""IU 8 "
- I8* * "
teristics of the Safe Shutdown Earthquake in
~
correspondans to the maaimum vibratory Width of tone paragraph V(s).
accelerations as outlined in paragraph (a) of re qu tring d e.
(d) Determinerion of Other Desten Condi-sectnon VI;and refled feutring in-tions.-(t) Soil Srsbility. Vibratory ground (v) Where the manimum vibratory accelers.
tions of the Safe Sh.stdown Earthquake at the Magnitude of s'estigation (See motion associated with the Safe Shutdown foundations of the nuclear power plant struc.
earthquake; flg. f)
Earthquake can cause soil instability due to tures are determined to be less than one-tenth Less than 5.5.
I a controlwidth ground disruption such as flasuring. differential the acceleration of gravity (0.1 g) as a result of 5.56.4 2 a controlwidth consolidation, liquefaciton, and cratering which the steps requwed in paragraphs (a)(1)(i) 6.57.5 3 x control width is not directly related to surface faulting. The through (iv) of this sectum, it shall be assumed Greater than 7.5 4 a controlwidth following geologic features which could affect the foundations of the proposed nuclear power that the mansmum vibratory accelerations of the Safe Shutdown 1:arthquake at these founds-The largest magnitude earthquake related to plant structures shnu be evaluated taking into tions are at least 0.l g.
the fault shan be used in Table 2. This secount the information concerning the (2) Dercrminettom of Operering Bards Earth-earthquake shan be deterrhined from the infor*
phyEICal properties of materials underlying the l
que&c. The Operating Basis l arthquake shall be motion developed pursuant to the requirements site developed pursuant to paragraphs (a)(3),
specified by,the applicant af ter considering the of paragraph (b) of Section IV for the fault.
(3) and (4) of Section IV and the effects of the seismology and geology of the region surround-taking into account the information required Safe Shutdown Earthquake:
ing the site, if vibratory ground motion by paragraph (b)(7) of Section IV. The control (i) Areas of actual or potential surface or enceeding that of the Operating Basis Earth-w6dth used in Table 2 is determined by subsurface subsidence, uplift, or couapse quake uccurs, shutdnwn of the nuclear power mapping the outer limits of the fault traces resulting from:
plant will he required. Prior to retummg opera-from information developed pursuant to para-(a) Natural features such as tectonic de-
- tions. the licensee will be required to graph (b)(7)(iv) of section IV. The control pressions and cavernous or karst terrains, demonstrate to the Commission that no func-width shall be used in Table 2 unless the particularly those underiam by calcareous of tional damage h.s occurred to those features characteristics of the fault are obscured for a other soluble deposits; necessary for continued operation without significant portion of the 10 miles on either (6) Man's activities such as withdrawal of undue risk to the l'ealth and safety nf the side of the point of nearest approach to the fluid from or addition of fluid to the sub-public. The maaimum vibratory ground acceler.
nuclear power plant. In this event, the une la surface. entraction of mlperals, or the loading stinn of the Operstmg Basis Earthquake shall Table 2 uf the width of mapped fault traces effects or dams or reservoirst and be at least one half the manimum vibratory more than 80 miles from the point of nearest (c) Regional deformation.
ground accelerstion of the Safe Shutdown appruach to the nuclear power plant may be (ii) Deformational tones sach as shears,
- l. art hq ua ke.
appropriate.
joints, fractures, folds, or combinations of these
, (b) Dercrmmarion of hercf to Design for The zone requiring detailed faulting investi-features.
e Surface Fau ttms. In order en deter mme s. sation, as determined from Table 2. shall be.
(!!!) Zones of alteration or irregular
$ whether a nuclear power plant is required to beS used for the fault oncept where:
$ weathering profiles and tones of Structural
% deugned to withstand the effect9 of surface:
(i) The rune requirms detailed faulting: weakness composed of crushed or disturbed the location of the nucless powerE investigation from Table 2 is less than one-halfE materials.
E faultin g,
) plant with respect in capable faults shall he$ mile in width. In this case the tone shau be stI (iv) Unrelieved residual stresses in bedrnck.
(v) Itocks or sous that misfit be unstable a
considered. The erva neer which each of these least une-half mile in width:or a
a faults has caused surface faultmg in the past is (ii) Definitive evidence concerning the because of their mineralogy, lack of consolida-identified by mappmg its fault traces in the regional and local characteristics of the fault tion water content, or potentially undesirable vicinity of the site. The fault traces are mapped sustifies use of a different value. For esemple, response to seismic or other eventt Setemic along the trend "I the fault for 10 miles m both thrust or bedding-plane faults may require an response characteristics to be considered shall directions from the poin t of its nearest increase in width of the zone to account for the include liquefaction, thimotropy, differential appruech to the nuclear power plant because, projected dip of the fault plane;or consolidation, cratering, and fissurtn6 for esemple, traces may be obscured along (iii) More detailed three. dimensional infor.
(2) Slope Ste6stify. Stabdity of all slopes, portions of the fault. The manimum width of motion, such as that obtained from precise both natursi and artificial, the fauure of which the mapped fault traces, called the control investigative techniques, may justify the use of could adversely affect the nuclear pow;r piant, w id t h.
is then determined from this map.
a narrower zone. Posaabte eaamples of such shall be considered. An anaessment shall be Because surface faulting has sometimes techniques are the use of accurate records from made of the potential effects of erosaun or occurred beyund the limit of mapped fault c!c eiy spaced drill holes or from closely deposition and of combinations of erosion or traces or w here fault traces have not been spaced, high resolution offshore geophy sical deposition with seismic activity. taking into account information concerning the physical previously recognized, the control width of the su fault is increased by a factor which is de.
delineating the zone requiring detailed property of the meterials underlying the site pendent 6pon the largest potential earthquake
.ating investigation for a fault, the center of developed pursuant to paragraph (a)(1), (3).
I related to the fault. This larger width dehnen" she zone shall coincide with the center of the and (4) of Section IV and the effects of the a done, called the zone requiring details fault at the point of nearest approach of the Safe Shutdown Earthquake.
faultmg investigation, in which the possibtlity fault to the nucleat power plant as illustrated in (3) Cooling Water Supply. Assurance of of surfste faulting la to be determined. The Figure I.
odequate coolms water supply for emersency following peresraphs outline the specific pro-(c) Determination of Desfgn Bases fer
.nd long-term shutdown decay heat removal cedures for determining the mone requiring Scismtcally fnduced Floods and werer Weves.
shall be canaldered in the design of the nuclear Jetailed faulting Investigation for a capable The aire of seismically induced floods and power plant. taking into account information fault.
water waves which could affect a site from concerning the physical properties of the ma-(l) Derrrminetton of 7pne Aequtrent either locally or distently generated seismic terials unde: lying the este developed pursuant Dr re88 cal Feudtina lavest(settua. The rune activity shall be determined, takir.g into con-to paragraphs (a)(l). (3), and (4) of section IV requitms detailed faulting invesugetlun for a sideration the results of the investigation and the effects of the Safe Shutdown Earth-i capahle fault which was mvestigated pursuant required by paragraph (c) of section IV. Local quake and the design basis for surface faulting.
to the regulrement of paragraph (b)(1) of topographic characteristics which might tend to Consideration of river blockage or diversion or Section IV shall be determined through use of modify the possable runup and drawdon at the other failures which may block the flow of the following table:
site shall be considered. Adverse tide conditions cooling wster, coastal uphft or subsidence, or shall also be taken into account in determining tsunami runup and drawdown, and fadure of the effect of the floods and waves on the site.
dams and antake structures shau be included in
/
The characteristics of the earthquake to be used the evaluation.=here appropriate.
%/
August 1,1980 100-6
]
t j
PART 100.e REACTOR SITE CRITERIA (4) Distant Struct tres. Those vructures Safe Shutdown Earthquake and under the could result in potential offsite e m posures whuh are not located in the immediate vicimty postulated concurrent conditions, provided that comparable to the guideline empusures of this
^
of the sate but which are safety related shall be the necessary safety functions are maintaaned.
part, In additlun to seismet lueds, including designed to withstand the effect of the Safe (2) Op erartan aests Esirnquake. The aftershocks, applicable cuncurrent functionsi Shuldown Earthquake and the desagn basis for Operating Basis Earthquake shall be defined by and accident induced loads shall be taken into surface faulting determined on a comparable response spectra. AD structures, systems, and account in the design of such safety features.
basis to that of the nuclear power plant, takmg components of the nuclear power plant neces-The design provisiuna shall be based un en into account the maternal underlying the sary for continued operation withost undue assumption that the design basis fut surface structures and the different location with risk to the health and safety of the puolic shall faulting can occur in any direction and asimuth respect to that of the site, be designed to remain functional and within and under any part of the nuclear power plant, e
applicet le stress and deformation limits when unless evidence indicates this assumption is not VI. APPLICATION To sutuected to the effects of the vihrstory motion appropriate, and shall take into account the I;NGINI TRING DFSIGN e>f the Operating Basia Farthquake in combina-estimated rate at which the surface faulting (a) Fibra tory Ground Morfo<s.-(l) Safe tion with normal operating loads. The may occur.
Shutdown Earraquake. The vibratory ground engineering method used to ensure that these (c) Sessmrally Indua rd Hoods and Water motion produced by the Safe Shutdown Earth
- structures, syste ms, and components are Warcs and Other Design Condisfuns. The design quake shed be defined by response spectre capable of withstanding the effects of the hasta fur seismically induced floods and water correspondmg to the maaimum vibratory Operatir.g Basis Earthquake shall involve the waves from either kically or distantly generated accelerations at the elevations cf the founda-use of either a suitable dynamic analysis or a seismic activity and other design conditions tions of the nuclear power plant structures tuitable qualification test to demonstrate that determined pursuant to paragraphs (c) and (d) determine pursuant to paragraph (a)(B) of the structures, systems and componenta can of Sectson V, shall he taken into account in the Section V, The response spectra shall relate the withstand the seismic and other concurrent design of the nuclear power plant so as to response of the foundations of the nuclear loads, except where it can be demonstrated that prevent undue risk to the health and safety of
' power plant structures to the vibratory ground the use of an equivalent static k>ad method the public.
motion, considerms such foundations to be provides adequate conservatism. The analysis or single-degree-of-freedom damped oscillators and test shall take into account soil-structure inter-neglectmg sod-structure interaction effects. In action effects and the espected duration of view of the hmated data avadable on vibratory vibratory motion.
I
[#
ground motions of strong earthquakes, it (3) R equired Jeismic tastrumentation. 2
,,,,, si,,,e a,,iuais ususuy wdl be appropriate that the response Suitable instrumentation shall be provide j so" spectra be smoothed design spectra developed that the seismic response of nuclear power i6 sE E m Ym from a series of response spectra related to the plant features important to safety can be 2 3
f nbratory motions caused by more than one determined promptly to permit comparison of f
8 l
[
earthquake-auch response with that used as the design hasta.
sumaa mesimen tosam The nucicar power plant shall be designed so Such a comparison is needed to decide whether h
, that, if the Safe Shutdown Earthquake occurs the plant can continue to be operated safely
% certain structures, systems, and components = and to permit such timely action as may be p
- will remain functional. These structures.% appropriate.
]
g systems, and components are those necessary to E These criteria do not address the neeJ for J" *8 m"'
[ assure (i) the integrity of the reactor cnolantIinstrumentation that would automatically shut F \\
gyryggggagte a pressure boundary, (ii) the capability to shut
- down a nuclear power plant when an earth.
reas swam eenpa down the reactor and maintam it in a safe quake occurs winich enceeds a predetermined cundition, or (iii) the capahdity to prevent or intensity. The need for such instrumentation is e
o,.m o, ma, mitigate the conseq uences of accidents under consideration,
~~
which could result in potential offsite es-(b) Surface Faultms. (1) If the nucle st pusures comparable to the guidelirie esposures power plant is in be located within the anne of this part. In addition to seismic load s, req uiring detailed faultang investigation, a ecludmg af tershoc k s, applicable concurren t deladed investtgatoon of the regional and local functional and accident. induced loads shall be geologic and seismic characteristics of the site FIGU R E l-DI AGRAMM ATIC IL LUST R A-taken into account in the design of these shall be carried out to determane the need to TION OF DELINEATION OF WIDTH Ol' safet y -related structures, systems, and cum-take into account surface faultmg in the design 70NE REQUIRING DETAILED FAULT-ponents. The desegn of the nudear power plant of t h.
nuclear power plant. Where it is ING INVESTIGATIONS FO R SPFCIFIC i
shall also take into account the possible effecta determined that surface faulting need not be N UCL F.A R l'OW E R PLANT LOCATION.
I of the Safe Shutdown Earthquake on the taken into accouunt, sufficient data to clearly
~
facdity foundations by ground disruption, such Justify the determination shall be presented in as fissurin g, d if f e re ntial consolidation, the ticense apphcation.
craterin g, liquefaction, and landsliJms, as (2) Where it is determined that surface f
required in paragraph (d) of section V.
faultang must be taken into account, the The engineering method used to ensure that applicant shall, in establishing the design basis the required safety functions are mamtained for surface faulting on a site take into accuunt Jurmg and after the vihrstory ground motaan evidence concerning the regional and incal assoc 6ated with the Safe Shutdown k arthquake se elogic and seir'nic characterlatica of the sate shall inv olve the u se of eit her a tult a ble and from any other relevant data-dynsmic analysia or a suitable qualification test (3) The design basis for surface fauttans tu demonstrate that structures, eyetems and shall be taken into account in the design of the components can withstand the setmis and nuclest pows? plant hy providing reasonable uther consurrent loads, encept where it saa he assurance that in the event of such displace-demonstrated that the uer of an equivalent ment h ?ing faulting certain structures, static load method provides eduquote conserve-systems,.nd components wiu remain func.
tasm.
tional. These struttures, systems, and com-The analyses or test shall take into assount punepts are thver recessary to assure (i) the sud-structure interaction effects and the anlegrity of the reactor coulant pressure espected durattun of nbratory mota n. It is tmundary (ii) the capabdity to shut down the I
i permissible to design for strain limits in escess reactor and maintam it in a safe shutdown
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of yield stram m some of these safety-related condation, or (iH) the capabihty to prevent or structures, systems, and components durmg the mitigate the consequences of accidents which i
100 7 August 1,1980 i
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AGREEMCNT
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I This AGREEMENT, ent red intq 1-y and between the COUNTY OF COLU:mIA, a politica
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subdivisica,of the State of 01Muu, by and thrcu-5 its Board of Commissioners,.
hereinatte: referred to a" "CNoty" Onct POETIANO GEERAL ELECTRIC COMPANY, an N
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Oregon corporation, horcincf tor refez. red to es *Tompany".
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EHEREAS, Co+pany is constru.-t ing the Trojan Nucl. ar plant on the shore of the Colunbia hiver; and UHEREAS, the safety requirem nts of the United States Atomic Energy Commission---
require that a cicar zono cr "cyclusion crea" he established around each licensed power reactor fac21itv: and UHEnEAS, portions of Colurbia County ronds are located in the exclusion area;
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and LH,EREA'S, the parties hereto wish to set forth the conditions under wh'ich l
Company car exercise the necesscry control over the portions of the county. roads included in the "cxclusion a'rea" in order to protect the public that might be
- I occupying the county roads or the county road rights of way in the event of a radiation cmcrgency; NOU TEREFORE, IT IS HERE3Y AGREED by and betwoon the parties hareto as follows
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County herchy agrees that residential use of and overnight camping in county l
roads end rights of vay with.in the exclusion aren 3n the Southeast one-quarter l
of the Northwesr cue-qu:rter, the Southwest one-quarter of the Northeast ona-quarter, and the Nerth 650 feet of the Northwest ene-quarter of the Southeast l
one-quartor of Section 2,, Township 4 North, Range 2 West, Willamette Meridian, shall be l'rchibited. Nonresiden tial activitics and uses. unrelated to the opera-tion of Company's adjacent reactor shall be permitted, specifically traffic on roads and rond naintenance by County forces. Upon notification to County, l
Co pany may remove er order the removal of all persons and their p cperty from County property when necessary to protect public health and safety.
1 II.
. In die event of an cre.rgency or threat ths.ccf, vhich ny af fect pcblic health or safety, County grants to Company the right to enter upon its lands within the e::clusion area and to remove persons and property therefrom.
County agrees to temporarily hald traffic when advised by Ccmpany that a radiation emergency j
exists at the Trojan Nuclear Plant that might unduly expose the public or County personnel.
III.
Notification to County should be made by telephone to the Columbi~a County Sheriff through the Central Dispatch radio facility.
In the event telephonic notification is not possible, notificatica by radio will be made' to the Central Dinpatch radio facility.
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IV.
t It is hereby agreed between the parties that this c.greement covers the entire width of the rignt af w.)y with. n said Section 2 us <Tescribed in paragraph 1 4
1 horcimibive.
L'Hr3EI'OD E, the part ims hereto have authoti.e.cd th'ic agreement to be duly cxecuted by Count.y purnuant co autho:-1: ation by it's Ecard of county Coir. mise.ioners at'its meetinej on.lu.y 3, 19J4, t.r.3 Crerany by iw duJy.muthori zed representatives.
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Dated at S t. Ucleic, Gregon thi 3rd day of Jul.y, 1974.
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ECARD OF COUNTY COi'J!ISSIONGRS l'OR COLUtGIA COUNTY, CREGCN f
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PORTIA!'D GENERAT, ELECTRIC COMPANY t Dy _
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DEPARTMENT OF TRANSPORTAilON
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g uu uso soonass UNITED STATES COAST GUARD Captain of' the Port m,
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U.S. Coast Guard
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6767 N. Basin Avenue Portland, OR 97217 Telephone:
(503) 221-6322 PIMORANDLH OF UNDERSTANDING BETWEEN U.S. DEPARTP2NT OF TRANSPORTATION, COAST GUAhD e
AND PORTLAND GENERAL ELECTRIC COMPANY TROJAN NUCLEAR POWER PLANT EP2RGENCY PREPAREDNESS AND RESPONSE h'
1.
BACKGROUND AND PURPOSE.
This memorandum of understanding establishes a framework of cooperation between the U.S. Department of Transportation, Coast Guard, I
and Portland General Electric. Company (PGE), Trojan Nuclear Power Plant, _
Rainier, Oregon (Trojan) in the planning for and response to radiological e:ergencies at the Trojan Nuclear site which may affect the safety of those using the Colu=bia River and adjacent navigable waters.
2.
RESPONSIBILITIES Portland General Electric Company is responsible for responding to
- all nuclear emergencies contained within the Trojan site boundaries'.
This includes responsibility for the safety of persons, property, and..the environ =ent within the Exclusien Area as defined in the Radiological E ergency Respense Plan.
The Coast Guard, Captain of the Pert, Portland, Oregon is concurrently responsible for the safety of persons, property and the envirencent in these. navigable waters and their i=:ediately adjacent shcrelines within his jurisdicticn (33 CFR 165). The waters and the 1 :ediately adjacent shorelines to the Trojan site are a part of this jurisdiction.
i 3
NCIIFICATION
- i In the event that a radiological emergency exists or is likely to occur that poses a threat to the public on or adjacent to the Columbia
' River or other adjacent navigable waters, PGE, the State of Oregon or other appropriate authority will notify the Captain of the Port, Portland, Oregon.
Notification can be accomplished by telephoning (day or night) the Coc=unications Center, Marine Safety Office, Portland, Oregon at (503) 221-6323 The Co==unications Center aleo continuously monitors Channel 16 (156.800 ch:), VHF-FM radio. Persons calling should request to speak with the Officer of the Day. The Officer of the Day, upon proper notification and call back verification, will contact the Captain of the Port or, in his absence, the Alternate Captain of the Port.
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4.
EXECUTION r
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Upon notificatien the Captain of the Port will initially close those
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waters within 10 miles (statute) of the Trojan site. This closure will be accomplished in the form of a Safety Zone as provided by 33 CFR 165 and will include the Columbia River from mile 62 to mile 83 and on the Cowlitz River up to 7 miles from its mouth.
In establishing the Safety Zone, the Captain of the Port will notify all appropriate agencies and persons, and make appropriate radio broadcasts.
e Once _the Safety Zone has been established, it will be patrolled by appropriate Coast Guard resources to ensure compliance with the terms of f
the Safety Zone. In additicn, Coast Guard personnel involved in the enforcement of the Safety Zone will distribute evacuation instructions to
. persons within its boundaries and provide assistance as needed.
Execution of the above task is expected to be accomplished within three hours af ter notification.
5.
COAST GUARD RESOURCES The Captain of the Port, Portland, Oregon has a multitude of resources at his disposal for accomplishing the above. tasks.
Included among these for immediate deployment are several small boats located at Marine Safety Office, Portland, Oregon and Coast Guard helicopters from Air Station Astoria.
It should be noted that these resources are available contingent on other operational priorities existing at the time f
of notification.
6.
TERMINATICN OF SAFETY ZONE The Safety Zone will remain in effect until such time as the Captain of the Port has been satisfied by appropriate authority that the danger no leager exists.
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Captain o the Port Portland Oregen A
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BATT D. WITHERS Date Vice President Nuclear Pcrtland General Electric Co.
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A G R E E ?! E N T
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This agreement entered into by and between the State of Oregon, by and through its Department of Transportation Highway Division, hereinafter referred to as " State" and Portland General Electric Company
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an Oregon corporation hereinafter referred to as " Company".
WHEREAS, Company is constructing the Trojan Nuclear Plant on the i
shore of the Columbia River; and WHEREAS, the safety requirements of the United States Atomic Energy Comission require that a clear zone or " exclusion area" be established around eac'h licensed power reactor facility; and W'EREAS, a portion of the lower Columbia River Highway No. 2W is H
located in the exclusion area; and WHEREAS, the parties hereto wish to set forth the conditions under which Company may exercise the necessary control over the portion of-the lower Columbia River Highway included in the "exclusi.on area" in order to protect the public that might be occupying the state highway or the state highway right of way in the event of a radiation emergency.
NOW, THEREFORE, IT IS HEREBY AGREED by and between the parties hereto as follows:
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1.
f State hereby agrees that residential use of and overnight camping in the exclusion area between Mile Post 41.11 and Mile Post 43.10 of the lower Columbia River' Highway shall be prohibited. Nonresidential 2:A-14
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activities and uses unrelated to the operation of Company's adjacent
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f, reactor shall be permitted, specifically traffic on the. highway and highway maintenance by State forces. Upon notification to State.
Company may remove or order the removal of all persons and their property from State property whan necessary to protect public health and safety.
j II.
In the event of an emergency or threat thereof, which may affect I
public health or safety, State grants to Company.the right to enter upon i
its lands within the exclusion area and to remove persons and property therefrom. State agrees to temporarily halt traffic when advised by Company that a radiation emergency exists at the Trojan Nuclear Plant that might unduly expose the public or highway personnel.
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III.
Notification to State should be made by telephone to the Emergency Services Division, Room 43, State Capitol Building, Salem; to~the District Office of the Oregon State Police; and to the Region Office of the State Highway Division.
IV.
It is hereby agreed between the parties that this agreement covers f
the entire width of the right of way between the mile posts set forth in paragraph I. hereinabov,e.
IN WITNESS WHERE0F, the parties have hereunto set their hand and seal the day and year hereinafter written.
The Oregon Transportation Commission, by a duly adopted delegation q
order, authorized its Chaiman or Vice C:
- to act in its behalf in
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approving this agreement. Approval was given for this agreement on June 13, 1979 by Chairman Anthony Yturri which approval I
is en file in the Comission records. The delegation order 'also authorizes the State Highway Engineer to execute the agreement on behalf of the Comission.
APPROVED:
STATE OF OREG0'N, by a'd through n
its Department of Transportation Highw Division j
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Stafe Highway Engineer
',, ksststint% tate' Highway Engineer 8
APPP.0VED AS TO FORM:
ORTLAND GENERAL. t RIC COMPANY f
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Asgs~tantAttorneyGener61 t
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C00!TN.!!VE AGREEMEriT l
j TilIS AGREE 11ENT uade and m:ciuded this 23ra day of July 1973, by and between the '3 TATE Or extG0tl acting by and through its State Land Board (h:reinafter referrcJ to a.s the " State") and PORTLAND GENERAL ELECTRIC COM! 5.NY, an Orgpn co.pc;t. tion (hereinafter referred to as the e
" Company"),
W I T H E S S E T !! :
WHLRCAS, the Co;;nny is constructing a ?!uclear Power Plant-(the --
Trojan Nuclear Plant) cn lands cdjacent to the Columbia River near Pres-cott, Oregon, under perr.its granted by the State of Oregon and the United States of Amrica, the latter cr.til:9 by and through its Atcaic Energy Cor. mission; and e-WHEREAS, the Cospany in fulfilling licensing requirements of the f
Atomic Energy C::=issic:.u:;t ::'?hlish an exclu:;ien area as specified in Titic 10 Coda of Feder0 Reguit.tions. Part 100, Section 100.3(a) and Section 100.ll(a)(1); and WHEREAS, i.he exclusion crea required of the Company in connection with the Trcjan Nuc1 car Plant will affect submerged and submersible land
[.;r.ed and c:atrolicd by the Sute; and 1 i j
WHEREAS, the State is authorized by Sub:;ection 2 of Section 5 of "I
Article VIII of the Oregan Const.itution to manage such submerged and sub-mersible lands for the benefit of the people of the State of Oregon; N0'.! TilEREFORE, ar.d in consideration of the Agreements hereinafter set forth, the parties hereto agree:
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Pege 1 - CGr; kATIVE ACT,EEMElil f
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- h. EXCLUSION AREA:'The following submerged and submersible
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lands of the State are hereby set apart as part of the exclusion area for the Trojan Nuclear Plant as that term is defined in Title 10 Code of Federal Regulations Part 100, Section 100.3(a):
A parcel of land in Section 1, Township 6 North, Range 2 West, and in Section 36, Town:; hip 7 North, Range 2 West of the Willamette Meridian, Columbia J
County, Oregon, more particularly described as follows:
Begi~nning at a point with Oregon Grid North Zone Coordinates N. 876,546.66 and E.1,394,66E.66 from l
which said point the West quarter corner of Section I
36, Township 7 North, Range 2 West, Willamette Meridian, bears N. 59 26' 26" W., 591.03 feet, said point also being the Northeast corner of that certain ~~
tract of land described in Book 103, on Pages 81, 82, and 83, Columbia County Deed Records; running thence S. 36* 46' 21" E.,.307.93 feet; thence S. 14 02' 10" E., 206.16 feet; thence S. 21
- 48' 05" W., 269.26 feet; thence S. 21* 48' 05" E.,
269.26 feet; thence
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South 550.00 feet; thence S. 23* 11' 55" E., 380.79 feet; thence S. 12* 05' 41" E.,
715.89 feet; thence
' S. 21* 48' 05" E., 538.52 feet; thence S. 5 42' 38" W., 502.49 feet; thence S. 22*-37' 12" E., 650.00 feet; thence S. 56* 18' 36" W.,180.28 feet; thence S. 80* 32' 16" W., 304.14 feet; thence S. 25* 06' 23" E., 1,932.59 feet; to coordinates N. 870,500 and E.
1,395,970; thence S. 43 13' 43" W., 580 feet more or less to the mean low water line of the Columbia River; thence Northerly along the mean low water line to the
' i South line of said Section 36; thence West along the said South line 70 feet more or less to the mean high
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water line of the Columbia River; thence Northerly along the mean high water line to a point on the North line of said tract of land described in Book
.t 168 that is N. 87 43' 01" 9. of the point of begin-ning; thence S. 87* 43' 01" E., 50 feet more or less to the point of beginning.
Page 2 - COOPERATIVE AGREEMENT
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Said parcel of land contains apprpximately 2G.8 acr..
of which 25.1 acres are submert;cd, and 1./ acres are
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suhmersible. All s..id. lands are shown outlined in red in tile c:ap attached hereto -and by this rar:rence mWe a part hereof.
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Residential use of.and overnigh. camping 2.
RESTRICTED USE:
in the exclusion area shall be prohibited by the' State.
Nonresidential activitics and uses unrelated to the operation c.f the Company's adja-cent reactor shall be permitted only when no significant hnard to pa'r ~
'I lic health and safety exists and then only under appropriate limitations
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as in this Agreement provided.
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3.
USE LIMITATI0i!S:
In mandging its larids tiinin the above-I described exclusien area and in sales ~and leases 51adelAtli respect to such lands, the State will insert in cach Deed, Lease, fasement.
Permit or other'~ instrument granted a provision t'o the effect tilat 'the "
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lands affected are within an exclusion area as thab term is defined by~
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the Atomic Ene' gy Con:nission; that such lands are subject to safety r
regulations established by the State, the Atomic Energy Conmission, and the Company with which the grantee shall comply'; and that the Company has a right to rcmove er order the removal of all persons and their property therefrom in compliance with said safety regulations.
4.
EMERGE!!CY PROCEDURES:
In the event of an emergency or threat thereof, which may affect public health or safety,'the i
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State ' grants the Company the right to enter upon its Iands with-in the exclusion area and to remove persons and property therefrom.
The State also grants the Company the right to proclaim safety regulations affecting persons and property occupying State owned Page 3 - COOPERATIVE AGREEMEllT f
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lands within the exclusion arca, which regulations upon approval by t
I the State shall he made by the State a part of every Deed, Lease, Ease-ment, Permit or other instrument issued by it as previously provided Such rules and regulations when so adopted shall also become a part of the State's management policy for the administration of such lands.
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5.
TERM: The term of this Agreement sha11 be for the life of the construction permit and operating license granted by the Atomic-- ;.
l Energy Comission for the Trojan Nuclear Plant.
6.
OTHER RIGHTS: The extent of Portland Genere f Electric
.u Company's authority over State owned lands described in this Agreement is limited to the establishment and enforcement of rules governing the removal of persons and property from the exclusion crea'in the manner.
set forth in this Agreement. With this exception, all right, title and interest in and to said lands shall belong to and remain in the State.
7.
The Company'shall indemnify and hold the State harmless frcm and against all claims and demands for loss or damage, including claims for property damages, personal injury or wrongful death, arising out of or in ennnection with the exercise of any rights or privileges granted to companies undcr the provisions of this Agrecmont.
In the event any such claims or demands are mada against.the State, the Company shall i
I pay all costs and expenses, including reasonable attorney's fees, in-curred by the State in connection with the defense of any such claims.
Page'4 - COOPERAT!VE AGREEMEi4T
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Ifl UITi!ES:. ;':!;:!:00F ih : pari.ics hereto have executed this i
Agreement as bele.: 'nri cribt.J on the day and year first above set forth.
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3 STATE OF OREGON J
by its STATE LAND BOARD
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PORTLA!!D GENERAL ELECTRIC C014PANY By:
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Vice President Attert:
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e Secretary AprF;O',';r.D A' O PCI.U p;{ittip" ".0'.];iu;i, EOL'. 310'.7 & Ii'S'X lh%-L, 7'.i.. <Y. '.e d.
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_A _G _R E _E _M E_ _N _T THIS AGREEMENT is made this da[e by and between PORTLAND GENERAL ELECTRIC COMPANY ("PGE"), a corporation, with general, offices' located at 121 SW Salmon Street, Portland, Oregon, and' BURLINGTON NORTHERN INC., with general offices located at 176 East Fifth Street, St. Paul, Minnesota.
WHEREAS, PGE owns and operates its Trojan Nuclear Plant located on the Oregon shore of th'e Columbia River and BURLINGTON NORTHERN INC.,' owns andoperlates a railroad through tihe Troj-an
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and Nuclear Plant premises; i
WHEREAS, BURLINGTON NORTHERN'INC., is willing~to limit uses and permit PGU to exercise jtifisdiction over certain parts of its land in accordance with-the provisions herein; now, therefore, N-IN CONSIDERATION of the mutual covenants herein, it is agreed as follows:
(1) There is hereto attached, marked Exhibit "A" and made a part Of this Agreement, a plat showing BURLINGTON NORTHERN INC'S., right of way within the area of PGE's Trojan Nuclear Plant (" Area").
This Agreement covers that portion of BURLINGTON NORTHERN INC'S., right of way shown in yellow on said attached Exhibit.
(2) PGE is hereby granted authority and permission to remove 1
or order the removal of all persons and their property from the Area, except agents, employees and invitees of BURLINGTON 2:A-23 1
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,_ NORTH 5RN INC., and to exercise such privileges as though PGE were the owner of said railroad tracks and lands within the Area.
In addition, PGE is authorized to erect and maintain appropriate signs to advise any person within the Area of the--
limitaEion of use and exclusions provided f~or,herein.
- However, i.:
before any such signs are erected the content and placement of the signs shall be approved by BURLINGTON NORTHERN, INC'S.,
superintendent at Portland, Oregon.
(3) BURLINGTON NORTHERN INC., retains all rights to use its property for its own purposes and to carry on and operate and maintain a railroad thereon; and in so doing, its agents, employees
-i.
and invitees shall have unrestricted access to the Area, except at such times as there may be a radiation emergency as herein-(
after provided.
Residential use and overnight camping in the Area shall be prohibited.
(4) In addition to the authority granted to PGE herein, when advised by PGE that a radiation emergency exists at the Trojan Nuclear Plant, or a threat thereof which might unduly expose the public or railroad personnel, BURLINGTON NORTHERN INC., agrees to temporarily halt rail acti--ities and traffic over its track and within the Area for thc tion of such radiation emergency i
or threat.
(5) The privileges
~~E herein may be performed without prior notificati
~ ORTHERN INC., (except for sign approval as here owever, as soon.as
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E practicable, following the exercise of such privileges, PGE shall notify BURLINGTON NORTHERN INC., thereof, including the facts and i
l circumstances surrounding the events.
Such notification shall be made by telephone to the Chief Dispatcher (285-5095 at Portland, or 695-0106 at Vancouver) and confirmed by letter to the Portland Division Superintendent of BURLINGTON NORTHERN INC., at PO Box 571, Portland, Oregon 97207.
In the event of a change of telephone numbers or a change of address, or either, no'tification'shall be in accordance with such change.
(6) In consideration of the rights and 'priv'ileges granted
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hereby, PGE shall indemnify and save harmless BURLINGTON NORTHERN INC., SPOKANE, PORTLAND and SEATTLE RAILWAY COMPARY, and all other persons or railror.d companies lawfully using the railroad right of way within the Area, from any and all claims, suits, losses, expenses, damages, delay claims and detour losses and expenses, whether or not any of the same may be contributed to by the action or negligence of BURLINGTON NORTHERN INC., or any of the said companies, their agents or employees, arising or growing out of exercise of the rights and privileges granted to PGE herein.
(7) This Agreement replaces that certain Agreement between the same parties dated November 20, 1973.
DATED this 2 M day of IU b/
, 1978.
t PORTLAND m ::CPAL ELECTRIC COMPANY
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' YW ATTEST:
a.po BURLINGTON NORTHERN INC.
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BY:f, w,m 2:A-25 i
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r AGREEMENT OOb II DdI
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Portland General Electric Company (PGE) is the operator of the Trojan Nuclear Plant (Trojan), which is located in Columbia County, Oregon, directly across the Columbia River from Cowlitz County, Washington. PGE maintains a radiological emergency plan and staff capability to implement protective actions onsite and to notify and advise offsite agencies in the event of a radiological emergency. Cowlitz County De,partment of Emergency Services (hereafter referred to as Cowlitz County) maintains a response plan for radiological emergencies which includes specific provisions related to Trojan. PGE and Cowlitz County entered into an Agreement approved May 13,.1974, with respect to specific Agreements necessary to the implementation of-the'se emergency response plans.
The Nuclear Regulatory Comission's (NRC) and the Federal ~ Emergen~cy Managemerit' Agency's (FEMA) regulations for radiological emerg,ency plans require that all emergency planning agreements between licensees such as PGE and. local agencies such as Cowlitz County be updated to reflect revisions to the if censee's emergency response plan. This Agreement is designed to comply with such NRC and FEMA requirements between PGE and Cowlitz County with respect to the im-plementation of their respective emergency response plans.
PGE and Cowlitz County hereby agree as follows:,
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The Agreement between PGE and Cowlitz County appro' vied'_-'
May 13,1974 is superseded by this ' Agreement.
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Cowlitz County will maintain and implement radiological.
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emergency plans and procedures for the Trojan Nuclear Plant which are acceptable to FEMA and NRC. Both PGE and Cowlitz County will keep each other advised of the status and any changes to their respective radiological emergency response plans.
3.
PGE and Cowlitz County will participate in drills and exercises as prescribed by FEMA and NRC to evaluate and maintain their respective plans in a condition of readi-ness.
4.
The costs incurred by Ccwlitz County for emergency planning activities as described in the Trojan Radio-logical Emergency Plan, including costs of the county's participation in drills 'and exercises shall be paid by PGE. The cost shall be $35,000.00 annually, and will be advanced to Cowlitz County in semi-annual payments beginning July 1,1981, with subsequent payments every 6 months.
2:A-6 Amendment 1 (Augusc 1981)
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AGREEMENT
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5.
PGE shall maintain a short-wave, tone-controlled radio base station at Cawlitz County Communications Center.
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Cowlitz County personnel will cooperate in testing this communications line.
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6.
PGE shall insta11' a~ Public Notification System within n an approximate 10-mile radius of Trojan. This Public Notification System shall. consist of a radio-controlled network of sirens activated by tone encoders. One of these tone encoders shall be located in Cowlitz County-
.at the Cowlitz County Communications Center. Within. the types of activities, contemplated by this agreement, Cowlitz County shall have control of the operation of the Pub"lic Notification,5ys, tem in Cow.itz County. cr 2
7.
PGE shall maintain a Dedicated Communications System located in the Cowlitz County Emergency Operations Center ~-
for communications between PGE, the States of Oregon an.d,
Washington, Columbia County and Cowlitz County. Cowl i tz' -
County personnel will cooperate in testing this Communi-cations System.
8.
In the event of a raciological emergency at the Trojan ~
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Plant, PGE will keep Cowlitz County fully infonned via
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the Dedicated Communications System or the radio system described in Paragraph 5 of all protective action recom-mendations made by PGE which affect Cowlitz County. The protective action recommendations will include appropriate explanations as to the reasons why the recommendations were made. PGE, if requested, shall supply a technical advisor to the Ccwlitz County E.O.C.
9.
In the event of a radiological emergency at. Trojan as described in Paragraph 9, all public liability resulting from such radiological emergency shall be assumed by American Nuclear Insurers, subject to the provisions of the Price-Anderson Act, as amended.
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10.
In the event of a radiological emergency at Trojan which
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is declared by PGE to be a Site Area Emergency or General Emergency, PGE will assume liability for those costs incurred by Cowlitz County and its political subdivisions which are over.and above expenses for normal every day operation and which are approved by the Public utility Commissioner of Oregon for inclusion into PGE's rate base and not to exceed $50,000.
Amendment 1 2:A-7 (August 1981)
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f " AGREEMENT hl. This Agreement shall remain in force until cancelled upon 90-days written notice by either signatory and shall be reviewed and updated by PGE and Cowlitz County annually
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by mutual agreeme'nt on or before July 1 of each year.
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Th9 parties hereto have executed this Agreement this [d day of I o L 1981.
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APPROVED AS TO FORM:
PORTLAND GENERAL ELECTRIC COMPANY d.
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By:
Assistant Ger)(p61 counsel Bart D. Withers, Vice Presicent V
Nuclear
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APPROVED AS TO FORM:
COVLITZ COUNTY:
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'Chai rman,- Cowl i t: i~ s E.5. Council
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2:A-8 A=end=ent 1 (August 1981) 1 sn e
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AGREEMENT This is an agreement between the State of Washington (Washington) and Portland General Electric Company (PGE).
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WITNESSETH WHEREAS, Portland General Electric Company's Trojan Nuclear Plant is located in Columbia County, Oregon, directly across the Columbia-j River from Washington State, and in accordance with the Nuclear Regulatory Commission (NRC) requirements for nuclear power plants, PGE maintains a Trojan Radiological Emergency Plan and staff capability to implement protective actions onsite and to notify 3
and advise offsite agencies in the event of a radiological emergency; and WHEREAS, PGE is responsible during drills, exercises, Unusual 4
Events, Alerts, Site Area Emergencies.and General Emergencies for keeping Washington governmental agencies fully informed via a i
dedicated communications system of conditions at the Trojan -
Nuclear Plant and of protective action recommendations'made by PGE which affect the population of Washington in a timely manner as prescribed in the appropriate regulations, plans
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procedures and which include appropriate explanationand s as to the reasons for the recommendations; and WHEREAS, Washington has developed radiological emergency response plans and procedures for the state including specific provisions for the Trojan Nuclear Plant; and WHEREAS, PGE and Washington entered into an agreement executed on July 17, 1980, with respect to specific agreements to develop such emergency plans; and WHEREAS, The Washington Departments of Emergency Services and Social and Health Services 4nd the Energy Facility Site
' Evaluation Council share responsibility at the state level for the preparation and implementation of such emergency response l
plans and procedures; and WHEREAS, PGE and Washington recognize the need for Washington to maintain a continuing emergency response capability during the operating life of PGE's Trojan Nuclear Plant; and WHEREAS, Both of the above referenced parties are desirous of entering into an agreement to ensure that Washington has adequate plan maintenance and response preparedness capability for responding to a fixed nuclear facility (FNF) emergency at PGE's Trojan Nuclear Plant; Amendment 1 2:A-51
, August 1981)
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' consideration of the terms and conditions f
NOW, THEREFORE, In contained herein, the parties hereto agree as follows:
i The agreement between PGE and Washington executed on 1.*
July 17, 1980 is superseded-.byathis ; agreement.,,,,,
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Both PGE and Washington will keep each other advised of the 2.
status of and any changes to their respective radiological emergency response plans, to include exchanging information --
and the J
regarding proposed changes in format, content, status of all pertinent emergency response plans, procedures, checklists, etc.
PGE will submit revisions to the Trojan radiological emergency plan and applicable procedures affecting Washington state agencies to the En, rgy Facility Site e
Evaluation Council for review and comment by the Washington state agencies signatory to this agreement concurrently with
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submission.to NRC.
3.
In accordance with NRC and Federal Emergency Management Agency (FEMA) regulations, PGE will be responsible for 3c-providing a plan and program for response to a. nuclear emergency at the Trojan Nuclear Plant.
The State of Washington will provide a plan maintenance and
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response preparedness capability in accordance with NRC and FEMA regulations to respond to a FN7 emergency at the Trojan
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Nuclear Plant.
The State of Washington, acting by and through its.
Departments of Emergency Services (DES) and Social and Health Services (DSES) through interagency reimbursement contracts with the Energy Facility Site Evaluation Council l
and any other necessary agencies, will perform the
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(EFSEC) emergency response planning services.
.,g.7 PGE and Washington will participate in drills and exercises 5.
as identified in the Trojan Radiological Emergency Plan and as specified by FEMA to evaluate and maintain their respective plans in a condition of readiness.
Such drills and exercises shall be scheduled in accordance with FEMA requirements and the needs'of the state and include an i
annual exercise of the Trojan Radiological Emergency Plan.
Upon implemention of the emergency response plans for the Washington Public Power Supply System nuclear power plants within Washington, Washington may elect to fully exercise its emergency response capabilities in the Trojan Nuclear Plant annual exercise on a less frequent basis, but not less than once in each 3 year period.
6.
PG'E 'shall reimburse Washington for the costs a'ttributable to providing the emergency response planning services authorized under this agreement in amounts not.to exceed those shown below provided that:
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Amendment 1 2:A-32 (August 1981) t
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The amount.cf eimbursement obligated to Washington j
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during the t(r. of this agreement shall not exceed
$120,000.00
.t: the work authorized under this agreement.
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b.
EFSEC will bill PGE for costs incurred by Washington under this agreement.
PGE will reimburse Washington j
for actual expenditures on a quarterly basis and EFSEC --
will disburse funds in accordance with state accounting procedures.
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The time period covered by this agreement shall be.from July 1, 1981 through June 30, 1982 (fiscal year 1982).
j This agreement shall be reviewed and renewed annually by PGE and Washington.
The annual review shall commence no later than four (4) months prior to the expiration of this j
agreement.
8.
PGE or Washington may at any time request changes or modifications in the scope of this. agreement.
Such changes i
including extraordinary or unforeseen work, any increase or i
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decrease in the cost of, or the time required for performing such work, which are mutually agreed upon by PGE.and Washington, shall be incorporated in written amendments to I
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this agreement.
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1 9.
PGE shall indemnify and hold and save Washington, its officers, agents, and employees, harmless.from liability of any nature or kind, including costs and expenses, for or on account of any or all suits or damages sustained by any person or persons or property arising out of performance of i
this agreement, except for liability which arises out of j
intentional or willful misconduct on the part of Washington, its officers agents and e=ployees.
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10.
This agreement shall not be construed as granting any governmental agency of Washington jurisdiction over nuc1* ear energy facilities in the State of Oregon.
11.
This agreement sets forth in full the entire agreement of the parties in relation to the subject matter hereof.
This agreement may be waived, changed, modified, or amended only j
by written agreement executed by both parties hereto. -
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he d ent 1 2:A-53 l
(August 1931)
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IN WITNESS WHEREOF, the par ies hereto have es:ecuted tihis agreement this J[
day of
,1981.
STATE OF WASHINGTON Ey Hugh Fowler, Director State of Washington Depart:nent of Emergency Services By M
Jppn A. Beare, M.P.S.,
M.D.
Iffrector Health Services Division State of Washimgton Department.of Social and Health Services APPROVED AS TO FORM:
By a
M By Kevin M. Ryan
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Nicholas D. Lewis Q hairman-
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Assistant Attorne7 General Washington State Energy Facility Site Evaluation Council
. APPROVED AS TO FORM:
PORTLAND GENERAL ELECTRIC COMPANY
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r By ad By Attornfg Ba'rt D. Withers V
V, ice President, Nuclear O
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A=end=ent 1-2:A-54 (August 1981)
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,ci ~o 3 01Uity Eo 34/u 1p DEPARTMENT OF COMMUNITY DEVELOPMENT PHYSICAL PLANNING
- CODE ENFORCEMENT
! c__N w.ou.r-oiwi so.r. mso -s i~cro~.ur.. m9;o~i as 3diiLT ~-' #
Octobe~r 29, 1981 Mr. Robert Clark, Branch Chief
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Operating Reactor Branch 3 U.S. Nuclear Regulatory Commission
,ashington, D.C.
20S55 W
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Proposed Coal Export Facility Across-Columbia"Riv'e9.'from
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Trojan Nuclear Power Plant
Dear Mr. Clark:
,This office is currently processing a Shoreline Management and Flood-plain Management permit for the' Port of Kalama.on~a proposed Coal export facility north of the mouth of the Kalama River'.
The proposal is located directly across the Columbia River from the Trojan Nuclear
- -Power Plant in Oregon.
.w It was recently brought to our attention that an exclusion zone exists around the power plant.
The attached map shows the exclusion area ex-tending to the east' bank of the Columbia River in the locale of the proposed coal port docks.
In order to understand how the presence of this :one might affect our Shoreline and Floodplain permit processing p ocedure, we would very much appreciate answers to the following questions.
1.
What does an exclusion area mean?
2.
Should the presence of the :one at Trojan affect the County's processing of the Shoreline and Floodplain permit applications?
How'could such a':one affect the proposed development?
3.
What is being done in terms of emergency planning and preparedness in anticipation of coal port development?
Since we would like any problems associated with permit processing identified as soon as possible, we would very much appreciate a hasty response to this inquiry.
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6 Mr.. Rob'ert Clark, Branch Chief.
October 29, 1981, j
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Should you have any questions or need any furth' > information, please t
contact myself or Sarah Deatherage at 577-3055.
Thank you for your cooperation.
t Very truly yours, tg i
Mar in arty, Ditector i
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