ML20072U145
| ML20072U145 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 10/11/1961 |
| From: | Engelhardt T US ATOMIC ENERGY COMMISSION (AEC) |
| To: | SAXTON NUCLEAR EXPERIMENTAL CORP. |
| Shared Package | |
| ML20072T843 | List:
|
| References | |
| FOIA-91-17 NUDOCS 9104190029 | |
| Download: ML20072U145 (31) | |
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George F. Trowbridge. Esq. ' (
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Thomas F."Engelhardt, Esq.i':h' N
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For the Staf f of the Atomic Energy Commission p o y, m n ;. q, a
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. This proceeding is Itmited to a regoest, filed, pursuant to 74
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3 This instant request rotates to conventional startup activities for.
a power reactor, including initial core loading and installation of..
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in. core. instrumentation, measurement of a variety of cora parametere n oam I
and operation at successive power levels up to the reactor's nominal q
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The applicant herein is Saxton Nuclear Experbantal 7
Corporation, (Saxton) a non profit corporation,Nartered under 4,
h k the laws of the Commonwealth of Pennsylvania, which was ~ fonneds gige 3
in 1959 by the four operating electric utility subsidiaries of lJp F M$.Mh Qi(%)di t i on to those w.Y)g^ l", ',,,,
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4 On August 3,1961, the Commission issued its Motica pro. TfM
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viding for heariQl'on September 6,1961 on the application by 4
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Whether the technical information omitted from and required to complate the application filed by We c'4 ew%yr applicant has been submitted) pI,
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Wether the construction of the f acility has proceededQ7 and there is reasonable assurance that the f acility.'"; t,,,
will be completed, in conformity with the construction ff,.
I permit and the application, as amended, the provisionsg 'f-of the Atomic Energy Act of 1954,.as: amended, and thed - '
rules and regulations 'of tho'Commisston11p-pp h.
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."3. ' Wether there is reasonable assuranc(that lthe activt
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?'eafet'y"of the public *and thit#euibfEtisities,irt11'd i-be conducted in coup 11ance with' the lAtomis Energy Act as;of.1954,ee.amendedandtheerules;.landtregulationsof gr b,
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Phether.the applicant <is technically and financially 06 b.
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4 The hearing was held on the designated date at which both
$axton and the Staff presented evidence in support of the issuanca of a provisional operating license. There were no intervenors in the proceeding and there was no one who desired to make any other appearance or statement at the bearing.
The Saxton reactor is of the pressurised water, thermal neutron, hetrogeneous type, utilising 5.7% enfiched uranium dioxide as the nuclear fuel, moderated and cooled by Itght vatte.
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At its normal operating tettperature and pressure, the reactor will develop 20 thermal megawatts of power. ' The~8' auto'n reactor '""lT*"'d " '"
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Belgian reactor, Br 3 (40 thermal megawatts), both of which were
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x many components and syst. ems whose reliabil,ity has been, establisbed# N 4 Much of the detailed design ande....t; pg
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The core of the reactor consists of 21 fuei assemblics ar "
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JJ Westinghouse Electric Corporation executed:hhf$pt w.. py x. y a m.3 q w ;,
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'1/ Tlie Beigiaf reNtor wasinot inopersNdn'. at'date of the, hearing (.Q,'.1
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3 circular cylinder. Each fuel assembly is composed of 81 indi-I vidual stainless steel fuel tubes, filled for the most part with 5.*/% anriched uranium dioxide fuel in the form of cylindrical ceramic pellets. The fuel assemblies are held in proper align-ment by an upper and lower core support plata each of which is perforated to permit the light water coolant to flow through the core to remove heat. Although the initial core will con-tain only-21 fuel assemblies, the support plates are designed to allow for a total of 32 fuel assemblies. The core has been designed to provide a ratio (Departure from Nucleate Boiling
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inner barrel through the outer layers of the vessel is provided in order to monitor for any leakage from the stainless steel shell.
The Saxton multi-layer pressure vessel was the subject of a detailed review by the Staff of the Conraission and the ACRS.
v, The use of a multiple layer vessel represented a change from Saxton's original proposal of a solid vs11 pressure vessel. The "MA 8/
ACRS reported that in its opinion a change to a multi-layer pressure vessel designed and constructed specifically for thi m
Saxton reactor would not introduce any additional hazard to,thag;.gg health and safety of the public. The Staff concurred in thtele4 k. 3,,.,
s um opinion, subject to any operating experience to be gained froad.
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operation of SPERT III, a reactor, also utilizing a multi-layerpj pg..
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ot unusual ef fects. Therefore, the Staff has now concluded onY" * '
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'lSince a large enount;of reactivity has to be contro11ed'by a ismall number of rods /each rodLhas'to be of high wofthTand@ % -
there is the possibility that the reactor can be made*dritical
,by complete withdrawal.of a single control rod. A; system in-volving manually set 11mit. switches is provided to preventHf t;'
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7 the basis of the available information that the Saxton multi-layer pressure vessel would not introduce any additional hazard to the health and safety of the public.
The othat components of the primary cooling system, in-cluding the steam generator, main coolant pump, piping and fixtures are of conventional design, and have been sized for operation at power levels up to 28 thermal megawatts during the future experimental program. The system has been represented to be adequately instrumented to measure temperature, pressure, and flow, with indicators, alarms, and control signals provided as necessary to operate the main coolant system safely and effi-ciently.
The Saxton reactor uses a combination of methods to control the reactivity of-the core similar to those successfully used 15
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The primary method utilizes six offset cruciform shaped control blades containing a silver-indium-cj.,.
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cadmium alloy which is nickel-plated t9 increase the corrosion
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8-The motive power for moving the control blades within the core, as required to regulate the power of the reactor, is pro-vided by a friction grip magnetic jack type drive mechanism, 1/
which is similar to the design of the Belgian reactor, and thua differs from the latch type grip used in the Yankee reactor.
Although the control blades of the Saxton reactor are the bottom entry type, they are lifted above the core during ' operation and are designed to f all into the core under the force of gravity during reactor scram. It is expected that the control drive mechanisms combined with standard control instrumentation, scram circuits-and interlocks will provide safe control of the Saxtoo" re actor.
When the reactor is at operating temperature and pressure -
m the six control blades possesc reactivity (poisoning capabili.ty)
., vy values expected to be sufficient to shut the reactor down with gg an adequate safety margin even though the rod of highest worthQ sticks ou~ti of the cora. A manually set limit switch is pro
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a cold condition, the control blades do not provide a suf ficient
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the7 operating. experience of the Belgian reactor was not ava11ableg%.1 for consideration, since its startup program had not been initiated.
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poisoning effect to hold the reactor in a sub. critical con.
dition. As in the case of the Yankee reactor, a secondary con.
trol system is utilized for cold reactor shutdown in which a soluble nuclear poison, boric acid, is added to the primary coolant system in sufficient quantities to maintain the reactor in a shutdown condition. During reactor startup, as the teopero ature of the system increases, the dissolved poison is gradually removed from the primary coolant by a bleed and feed process.
The feasibility and safety of this method of controlling a reactor undar shutdown conditions are stated to have been e *~
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s cessfully deacastrated in the operation of the Yankee reactor.
W;c l, A standard system of instrunentation is provided te continuously monitor and measure the flow, temperature, pressure, flux and. uJ power level of the reactor, which is expected to insure safe ', fy l 1
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operation from startup to full power conditions.
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cuit is provided to actuate the rapid insertion of all rods "$ps%M/A1 n.6N3k W 3'M UA W j
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c..w..,_In. addition, a rod stop circuit is provided for use;duriinscr r:
i plant startup which will block the re 1 of control' rods th h i
event a f ast startup rate exists'.' The system includes an
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automatic control circuit which can be used during steady state operation to move a single rod or a selected group of rods to maintain a constant power level. The Saxton control system also s.
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viously described for the purpose of varning the operator of i
abnormal but not necessarily unsafe conditions.
9 A high pressure scram is not provided. The main coolant fystem is protected by relief valves against over-pressure.
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the pressure rises because of high power level or because the T
temperature in the primary system rises excessivaly, there are~~*
high power and high temperature screas. A safety injection, y system, which includes an 60,000 gallon storage tank, and two a y,
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the event normal reactor coolant is lost.
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- required to charge degassified and demineralized water from the f
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ice secondary plant'into the main coolant' system;')di%
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11 charges berated water into the nain coolant system when it is required to keep the reactor suberitical under cold shutdown conditions. The purification system establishes and maintains.
water purity in the main coolant system, provides control of hydrogen concentration, removes boric acid by a bleed and feed operation, provides a source of main coolant water for saapling -
and fission product detection and provides a source of make-up water to the main coolant system.
The system is also utilized c
to remove decay heat until the main coolant system temperature and pressure have been reddced sufficiently to permit operationjp! /
-?
~
w of, the shutdown cooling system. The chemical addition system,isq,g." ;
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<,heggnad to, prepare supplyboricacidforthemaincoolantgg.,
.e-
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system and the storage've11 system, to add hydrazine and lithium e l
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' hydroxide or potassium (hydroxide as required to maintain the -g 'p.
e.
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. oxygen content and pH of the main coolant water, and to add, it, dr."
s;J%p 7.p;g, y.
i-a e
j weg c,
e!.N%, necessary.. decontaminant solutions to remove radioactive cor--; w '
.@@' h
^ 1 4 4 b!di. d fl~
@ @ @pwUT'H % Twp h rosion products from the various plant syst"rt The components ty
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'hce.t%chiuser ano to transfer it to the river water. The shut :: r-y.. a h^?'M',;f stem is designed to remove decay heat,from'tha(k ['k(N C jj;j.,
v aRgt,.&; T
.,;r g.d down c,ooling,s,;y._., J. Q 4.0 n w:..,
r,,
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. d.,;: O A D t. %. v f4Cl$2 N!/W
.50C WJM h % 6 reactor core after the main coolant system pressure has been
.,I QY$y%s.&&DhWWW,;iQ4%Q;and to provide spar. d:g&&if$liQh&hh$h'y&e.4 f
in..Wiy?;u v %
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reduced to 150 ta
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ga 4a c ~w,w;y n.sw. :..
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12 for the purification ' system. The storage well system is intended to transfer storage well water to or from the refuelin8 vater storage tank as required for refueling operations, to purify and cool the stora'ge well vatar.d o_ provide a reservoir of water.t 9,,.
forsafetyinjection,andtoprovidewaterforflushingrefuelink equipment. The cooling, heating, and ventilation systems are m;4
. st4 provided to cool or hest and ventilate the various potentiallyUd,_
U@
radioactive, as well as non-radioactive areas of the plant. The.M 4
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station service electrical system supplies the power requirements, h L
.'4
~
.,g -
UN.
r for the main coolant pump motor,(the.arious auxiliary motor s
e %ec x
.. u.e w drive.s press.uriser heater.s.. lighting..s ventil.ating, control a..T,.,,myg;v'j.s, nd vJ'
.~
s
..m n y pgp w%
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commmication s.,ystesso ' The secondar,,y steam system utilizes tha: " g, -Q
,7 g &y g wy _
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. ~gu,p...-y4 A
M steam produced in the nuclear staam generator by converting rit;
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- .priai 4 M y
- (499.Q Wrj@ h 0 W
s t!
Q.pl X "
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L yQ ffpf'f^"L into electrical energy which is to be' fed into the Pennsylvan The pressure contrer r.NC@-
y@qQ?jpway power distribution system..Wi[pigt. p W 4r.
Electric Company g qrt gg
,t+ i and reliaf system pressurizes,tbo main coolant loop and mainta
- t. M b M A @ yf8/if41 & M M !r@r{1 @ M W W D M A T &
t.
u; f$
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'the operating pressure at. approximately 2000 7ta during staa
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4*
- Y' e m.,
^ %g ' ?. h AQ1]'v
'G, g.6 - 0.h $ %y994
. ration. iThe radiation men M;
- mvid W'
M W b m i.V @ $' M @ W @'
$ Eg "
MiM wnd indica d e p 6ior.1ou ivvci c4 uh a c.b^
,p,
' f# G \\ - } j ',!
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- 4 ' ?;
10caticus,in and around the_ plant. e~..o.s
+
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Radioactive wasta'disposs. systems' for solid liquid W
.S h f M ! M $ V % W 4%
jiU@/fFdah.a,
. N%),
% g.dg'a u
i gaseous wastos are provided for, the Saxton facility. The sol'id../
s w,.
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~
(*,
s' agu.s.wJu-gp+ agag;( g..,u.p, 3,,x. w@w %n w-n,.
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waste system will handle both combustible and non combustible i
radioactive materials, by placing them in'55-ga11on' drums, for 1
collection by an AEC licensee'fo'r ultimate disposal in Ccamission approved areas. Resins from tho' various purification' systems will be sluiced to one of three 800 gallon underground storage tanks for retention until ultimate disposal dan' be effected. 50 i
solid wastes will be buried at the Saxton site. The liquid vaste
.s disposal s' stem includes a 10,000 and a 5,000 gallon tank, each y
being of dual, or tank within a tank,~constru'ction for the storage of radioactive liquid affluents.,., Equipment. is also pro.m,
y.
s.
. -.- e m..
vided to add alkali to the acid wasta liquids in order to
'3 ".,.. c., _ w~ ' ^
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minimise the corrosion of the pipes and storage vessels. All
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,e piping' _is enclosed in concrete' troughs:or, double pipes whichp' 3
+
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,.1 will be monitored for leakage, as will the space between the
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. w. %g;vt: ~ x u
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,f double storage tanks. The liquids in the storage t k ill be -
AF l
. '.W)E.%%tMviFNW"i'4 MMNhf (@lS@an s wMNhDD M 3
U
' degass)ed, decontaminated and reduced to a sludge by means of a gas-3 '-
. g ey,p' orator"e'dulp'meSdMM ~
it a N111"'M"fL,
,, < g.r
, w ; ;2,,; 7 g,
C" y ::?,,aa&.
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'i
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cu % watnr am diactmat%
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f ter wait. wing, to the river at or below those flevels permitted,,, "
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.uc by 10 CFR Part 20. x.of the Commiss' ion's ' regulations for unrestricted J?..
-I
]
a.;
m: 2.&K. ', "
.I
< -. n @.
p areas.
a o\\ v y: ?:lkyhk.h$h&&.]V:h, Rb$$hh.* .L '.:. f .y. The gases from the liquid waste dLepo. sal: system and othern ' ' mf;s -
- w. r ;.-
7 sources.a,re first compressed for rete.ntion for. optimum radio m.,o.
- y,,gpm9 i
p.:. m - e.., n.. yn-o .,3 m;- .e. g s s N' h hf + ' ' ' * .4 [,[d. ',j [ t
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i ) 14 active decay and then are vented, under controlled conditions, to a common gas disposal system which is maintained under a Both slight negative pressure by one of two gas compressors. Saxton and the Staff have concluded that it is unlikely that any person will be exposed to concentrations of radioactive material in excess of that permitted by 10 CFR,Part 20. The Saxton reactor is housed in a steel containment vessel fabricated in accordance with the ASME Code and applicable code The containment is a vertical cylindrical steel vessel cases. 50 feet in diameter and 109 feet in overall height, with a hemispherical head at the top and an elliptical head at the bottom. The bottom of the vessel is 50 feet below grade with the c bottom head embedded in concrete. The portion of the containment vessel that is below grade has a 1% foot thick inner wall of re-inforced concrete which serves as shielding and provides reinforce-ment against external pressure due to ground water and backfilly and in addition providen missile protection. ,3 ,yx, 'as proposed that when thm r, ac R. e,. e n L at' i Q7 ; p m, the centu l m.., -essel r N oc closed and pressaic tight ~ with all acce'es openings, pipelines, and connections not required s fp +, c for operation sealed by 1cak-ti ht shutoff valves or gasketed 8 r ,o doors. Personnel will not be allowed to enter the containment vessel
- c ~.
when the reactor la hot critical or operating at power, -~ D r-l
- '3E-5
,3,11 . giv l
l ') i .? 15 Saxte>n has constructed its containment vessel of strength expected to be suf ficiant to withstand a peak internal pressure of 30 psig. This value was based on the peak pressure that was calculated as might be reached in the container if the entire contents, of approximately 2,500 gallons of water constituting the main coolant system (approximately 2,500 gallons of water) flashed to staats. A leakage rate test of the vessel, at the design pressure, and made prior to the placement of internal structures with the piping and electrical penetrations capped, resulted in a leakage rate value of 0.04% in 24 hours, but which was increased to an estimated value of 0.197% for 24 hours, by,... ~. taking iato consideration instrument and measurement error, possible leakage of electrical penetrations, and a reduced free volume when internal structures are in place. The Staff is ofq the opinion that the design, construction and method of testing 3. 8 of the containment vessel is a'dequate from a safety standpoint. ,,gfgg
- - t.
4 4 The site consists of approximately 150 a-res located about-Uberty ? eths of a mile from thE Boro W i t 3 ^-t hip, l u..J,5d County, Per 6, oppio.Ac ly w miles cast vi Ett.c.sburgh and 12 air miles wesc of tiarriseurg. The site lies between Tussey Mountain to'the west and Terracei Hountain to the east, and on the Raystown Branch of the Juniata b River. . - - ~ - g g s ZJ
- i ;.{i%. : 0 >
x ) .' 16 A micr6 meteor 61ogica1%etveth was set up.atithe site and
- 19 :
has been operated since Pkbruerfi 1960. in order'to establik estimates of dispersion and'diff6sion characteristice of the. ~ 11 The following conc 16sio 7n /. have been drawn as's result of site. analysis of the data collected during the period yebruary 6,1960, through January 19, 1961: (1) With' moderate lapse rates and una stable atmospheric conditions which exist 51 per cent of: the times effluent from the reactor wi11' diffuse vertically and transport. out of the site valley and into the main valley at elevations above ground level and moet of ten in a northeasterly direction w>, down the valley away from the sorough of Saxton. (2) With ine m c,. version and moderately stable atmospheric conditions which exist-49 par cent of the time, effluent will be restricted to the site-Lv valley with a predominantly low wind velocity, but turbulent air motion; the transport of effluent at this time will also be ,s.,e..- 9 n. ,o u.y .,9 - predominantly doieh,the valley away from the Borough of SaxtonM,p' .,.~ (3) The in~ lon and moderately stable conditt " u ? + 3 -nightchange[ tow /4+ hee {or'w'* ele 5, M y ',b r e. s conditione during[the by, d t a are cepected to prevr:a lens - periods of contamination buildup within the valley.. :(4) Deposip, tion of radioactt've particulate matter will be predominantly in'- gy.. a. . ~.. ISThe proceeding especting the Saxton construction permit was 4:'{ held on December. 15, 1959.-
- ^
11/ Subsequent to the hearing, the cotaments of the U.S. Weathek Bureau '. sions made at the hearNgdence. red in evidence as Ebce with.pho on Saxton's final safe arda report were in accord offe ibit A, w ich 'is hereby received in evi -,The cocoents are in substantial y< ' agreement with Saxton's conclusions. y ,st,
- b i-.,
- s s e
) a i 17 a northeasterly direction down the valley in an area which is
- =..:.b y ;.
very sparsely populated and which is almost completely covered by forests. (5) Washout of radioactiva particulate matter will take place predominantly in a direction south-southwest to south-west of the reactor. In this direction, the controlled property line extends for more than 3,000 feet. Consequently, it is expected by Saxton that the main portion of any washout should occur on controlled property. The general area around the Saxton site is presently sparsely populated, with a population density based on 1960 census figures of about 64 persons per square mile within a 5-mile radius The and about $3 persons per square mile within a 10-mile radius. residential population within one mile of the site is approximately 1790 persons and consis*.s primarily of the Borough of Saxton and the small adjacent comuetties of East Saxton and Stonerstown. f a construction permit to Saxton, a high Since the issuate V school with an enrollment of one'thousand pupils has been completsd
- s w tor.
at a dintencea spproximately 2.500 feet from the
- ~2 ia-1 m hill and out of t% ::
vi o ght m ve 4 0 reactor containment vessel av tht: nalculations made from the 1 data received, indicate that the predominant winds blow from the, site away from the school for all but a very small percentage of the time. Thus, in the event of a reactor incident, the school 1 + ~ \\ .f s, - - _ _ _ _ _ ^ - - - - ~ - - _i_
- ' - ~ - - T h / 18 c- = 5 is shielded by the hill from direct radhtion and, if the wind 'e 11 t' t is f avorable, would be protected by favorable meteorological g e t 11 / conditions from radioactive materials in the air. ~ v
- ey 9
Saxton has made calculations pertaining to evacuation programe g g to be effective in distances varying up to 2.000 feet from the i 1 reactor before direct radiation doses of 25 roentgens or a dose of =- i 300 rem to the thyroid from inhalation of radioactive iodine. These calculations were based on the assumption that the per' son ~ receiving the direct radiation dose renains in direct line of sight E from the reactor and that the iodine dose results from standing ~ -Q;g. y throughout the period of the exposure on the axis of a very narrow m -,fp tr E radioactive leakage plume in the path of the wind from the site'y r x ;s .o y The time available for evacuation of persons located at 2,000 % - ...-.v : gY5 s.... .. n,.. feet is calculated under these conditions to t>e five weeks for E s.x 3 .,;^... the direct radiation dose and four weeks for the dose to the = L , <, o.2 ~ A-a.. s.. ? h a*l,m.. = m b:., " thyroid. Furt'hePcalculations by way of extrapolating'from the r
- x..
n s, -
forrgC v re and extending the range to e d'r er 1
E-
' M ;.s l
x A ct of <ht
.. + n ' WO hio vind measurements were taken in the vicinity'. of the schoold;p
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a >
v',
xton's witness testified:
"When we first started the meteorological program, there vaa no hi h school there; elt was built after we started the ne work'f.th an we did not know about it at the time. So consequent y we didn't want to change our meteorological positions, which then might make all of our data insignificant. "'
~
however, that the data show no likely The Saxton calculations, are,d on that basis, addin 'another meteor.
Y to school children tan inj t
wn arror, rather than rendering the data insignif{d that. view, i station at the sc ool migh* have either con irme
-log cant. P P
.a.
or a
,LL,;l:YM0i'W
$5 N $,2): %, ; V '
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20 divided into two general categories: accidents involving an un-controlled insertion of reactivity, such as rod withdrawal at startup, rod withdrawal at power, beat extraction by steam plant valve failure or steam pipe rupture, introduction of cold water, and loss of chemical neutron absorber; and accidents involving inechanical failure of equipment such as a primary system rupture, control rod drive system failure, turbine governor failure, secondary system failure, and primary pump failure.
Saxton's analyses of the reactivity type of accident indi.
cate that the uncontrolled transient behavior of the reactor is
. e.,
such that the negative temperature coefficients of reactivity,
.., S.
the rod stop interlock, or.the scram circuits would terminate the
~
resulting power excursion before damage to the core occurs. Ttd '
-My;p Staff of the Commission agreed with the results of these analyses.
- M and believes that suitable design and procedural features have 1
,y #4 wyng a been provided to minimize the occurrence of these accident 6 'N" j, Of W e esi accidents analyzed, the %cr r 411v. er
- c ptpe
+ hire in the prim.
- . txa, t4
- .g c. 4
- d
.;t ; a f aibra of the scfety h.joulon system, le the inout severe and 3.,, y.s is considered by both Saxton 'and the Staff to be the "maximumVW,.. ' credible accident." Saxton concluded that rupture of a 3-in h Y Pipe constitutes the largest credible pipe rupture. 11owever in order to give an upper boundary for hazards beyond which no . c u; [f ^ l y g t
- E.
j[ - ,e 8 p 4 4
l .) ) s 21 credible,hazaEd could be expected to fall, Saxton analyzed a more 1 ] severe' loss of coolant accident-(which it calls the " maximum hyp'othetical ' accident") which assumed, among other. events, an instantaneous and complete discharge of all water from the I eprimary system to the containment vessel and a complete core 11/ meltdown. s The Staff was not prepared-on the basis of-information submitted by Saxton' and Westinghouse to accept the 3-inch pipe rupture:as the largest credible pipe rupture, but felt no need to pursue the matter further since it did agree that the " hypothetical maximum accident" postulated by- - Staten repre--
- sented.. in its Lview, the upper limit of public hazard that could _9, s
q - credibly occurduring operation of the Saxton reactor,,and that. -;p .in view lof..the remote possibility of occurrence'of an accident.h, ,. t' b. .w%, ~ of such severity, operation of the Saxton-reactor is an acceptable .w. - risk. - @d@~ ' # 'c l w Saxton's analysis of the " maximum hypothetical aceit,tr 4"" ; w p considn SEW ** radioactive materials which W1 N R
- c n
- .+
.w, i a reht.cd ch tis a>ula' mm ',na-M,-- the osait.es of radioactive <~, ~ B 1 material volch might leak'from the containment ves'sel,'and the [ k..; - , ;'gg
- s.?..
., s,. .a: ,a g, - direct radiation-and ingestion: dosages to which persons in the f QQN v'icinityLof the plant might be exposed. This analysis shows ,? h 0k & wea e h n n:,%? e m M/ Saxton did~not reflect computations of curie content of any releases . that might occur after a meltdown, excepc for Iodine and Strontium 89 and 90, while. indicating that major sources of gamma radiation could include Krypton, Bromine, Rubidium, and Holybdenum. D N " ,( r-l} j t j 'M-1' s i. 's~,i p ', g 4 "[ '
- g '
.y [~ k W' .f. e u..:n. -.m. .. _,,., -..., _ ~,
22 = ~ that, based on a limit for emergency exposure of 25 roentgens from direct radiation and 300 rem to the thyroid from inhalation of radioactive' iodine, not more-than 44 persons in the vicinity of the plant would have to be evacuated and that there would be ample time for evacuation. Regarding technical qualifications for operation of the reactor, the Saxton facility is being designed and constructed by the Westinghouse Electric Corporation who has had more than 20 years experience in the field of nuclear physics. The Saxton General Manager, Assistant Cenatal Manager and the three top supervisors for the site were selected on the basis of their ' academic training and experience received ca other nuclear projects. Other Saxton p'ersonnel' have been participating in a training, prog gram Obich includes (1) a general orientation course (2) specialty ' schools, '(3) re91 dent training at nuclear facilities, and (4).on- .ps the-job training at the reactor site, Personnel selected W 1s Westinghou m "se and train the Saxton par-a- ^r e. s, tbs p.,; w of inii:tal f ut; H-i. initia! 41ticainy, and wr* w paramecer measure 6ents, and will remain at Saxton for at Icast.two months, a'f ter a sufficient number of Saxton supervisory personneb and operators have been licensed to permit round-the-clock opera, tion atI'aubstantial'powerlevel. In addition, a Westinghouse react physicist, as well as other personnelevill be made available on I vet l <- j m.
) 23 - site' as a regular assignment to follow the preparation for reactor etartup fuel loading, initial criticality and physics tests to determine core parameters and reactor behavior. Saxton's Radiation Protection Enginest has had limited formal education and experience in health physics work, but he has had some engineering training and in addition, has completed l studies of basic radiological health and reactor environmental health studies. Saxton plans to continua to use the services oY consultants with more extensive health physics training and experience for assistance on health physics problems and analy-15/ tical wore. In addition, Saxton has retained the services of a" mechanical consultant to assist its Radiation Protection Engineer. Saxton-and Westinghoues have entered-into a contract underq which Westinghouse has agreed to (1) design, construct and fur-nish to Saxton the complete nuclear steam generating plant, a g, together with certain nuclear and non-nuclear supporting facili-ties;.(2) furnish all fuel requirements for the first five years l. ggp y + ,,r w e.,. of operation after initial criticality; and -(3) conduct a mu' stantial p m
- +.d post construction resear4 Es~ dai A Ed 7 5:~5 asi m U n I 9 ohysica,(Js ucu w re supplied Lu j
[, supplement the presentstion indicate. to em inadequate by the War-L' ing Examiner at the hearing. The Hazards Summary Report in refer-i ence to its radiological and metaorological program is.in gene _ral.,.. pattern terms concerning consultants and specialists but no indica-tion is given in that. report definitely identifying the persons,y intended to be utilized so that their qualifications could be nonessed. Saxton's. witnesses testified, :after inquiry, that actual contract. j relationships had been established with identified consultants, l and specialists recognized as qualified in the industry. The total l of the data on health physics,problema. and radiation protection is nov regarded as substantial evidence l sufficient to support the. con-clusions herein made respecting radiation safety. .m ~ 1 h'*ik Se: "[., p[ j d
- r r
r g
1 I ,) .D 24 development progra:n over a partod of approximately 7-1/2 years, including the furnishing of certain equipment and personnel. Saxton has agreed to pay Westinghouse the fixed sum of $6.250,000 as the full contract price for the reactor, plant equipment, fuel costs, materials and servicas to be supplied by Westingboose pur-suant to this contract. Westinghouse also agreed to assume financial responsibility for all special nuclear material needed for the five-year period of operation as required by AEC regula-tions, and to pay directly to AEC all ABC charges in connection with such material. In addition to the payment to Westinghouse of $6,250,000, 4 Saxton has agreed to bear the cost of certain modifications and additions to existing conventional facilities at the Saxton Steam. ws e,pr s - -Generating Station and to furnish certain other items and scr vices,.during the design and construction pbases of the project. ~ 6.i ~ y'ly Saxton has also agreed to baar1 the cost,of. operating the planti ' ' except fuel coetr M 'd to be. borne.by: Westinghouse.
- 2
,s 4. utimate_ sin w.'m o m 've ~ ~ ** the prgject *'n. ..;g .i*s P%=6cr 31,1992; i. e. thrcush ti. partod.co os covereo isy Lue t. Provisional operating license.3 are $7,367.056,., consisting of 9b m actual expenditures through June 30,1961[of $4,677,056, ,L.
- a. s h[
%b
- f
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h ) 25 and estimated costs for the period July 1, 1961, to December 31, 1962, of $2,690,000. This estimate covers payment of the total contract price of $6.250,000 to Westinghouse, the cost of modifications and additions to the existing generating station, the cost of operating the facility, including the cost of training operating personnel.. and miscellaneous other expenses. Saxton's ability to meet the financial requirements of the project depends on the contract arrangements,which are deemed adequate,which Saxton has made with the four' CPU operating sub-sidiaries to contribute predetermined shares of the expenses of the project. ly Saxton has made arrangements with NELIA for public liabil-ity insurance and has filed the necessary proof of financial protection in the form of a standard NELIA liability policy, providing coverage up to $1,000,000, and a letter from NELIA dated May 19, 1961, stating that NELIA it prepared to increase-t a..,,. .y.m., the limit of liability up to $3,600,000 v soon as the higher limit is needed 1 $3.600,000 is the amount c . gh? i,civ'~prcrcaron, cuwputce 1.. c * "4nce wit' nxi. 140 ut AEC's regulations, which wil'1 be required before the. reactor be-gins operation.' bThe designation"NELIA"coincidas.with the prevalent vogue of devising a sunmary of first letters from the insurance organiza-tion: Nuclear Energy Liability Insurance Association. 7 ,,;,, m h., f J ._____-________._-____-_m_._.-__
i ) 26 f Section 50.57 of the Comission's Ngulations permits the issuance of a provisional operating license prior to completion of the licensed facility upon a finding that there is reasonable assurance that the facility will be ready for initial fuel loading within ninety days from the date of issuance of the provisional operating license. The record reflects the current status of construction of the Saxton facility with a schedule that contemplates that the-Saxton reactor will be r6ady for initial fuel loading on or about November 15, 1961. There is substantial evidence of reasonabis assurance that the Sarton reactor will be completed in accordance, _ ~ wg. with the license application and will be ready for initial;fueli,. 3%fl ' ^ loading within ninety days from the date of issuance of a pro-3 L ..\\lQu visional operating license. Saxton has requested, and has presented WM[p - good cause to support the conclusion that this intermediate decision ,gy a should become imediately effective, in accordance with and .m q }Qqq g;.- -f zg y i.. L:p. e n w.: - ~ v subject to the provisions of Section 50,57(e). fyl> au 6 Section 50 m % * . desion's Regulations alen r 4",eadh'~i: %uul p u.ttag li, sne' include "a; . t iatefM ' > p Mr, pmistone wi' h respecs co any uncompleted items of construction". the provisional' operating license to be issued'ky[@y 1.., ....y s,. ..,, m,M h a.. %kccordingly, e ._ lf$([f Saxton includes a condition prohibiting operation of the Saxton ' l[j,f ,,,,. C :p t i,f., s < a.e
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s 2v. facNihy until the Director, Division of Licensing and Rogue lation, has found, and has so signified over his signatures that construction of the facility has been completed in cona formity with Saxton's Final Safefuerde Report; and -further requiring that a copy of such finding be promptly placed in the record of the licensing proceedings. A proviso to this con-dicion, however, would allow loading of the first. core and operation of the reactor with the re, actor head off and at a power level not exceeding 200 thermal kilowatts prior to a finding.of, completion of certain. enumerated systems. None of n the,anumerated systems is-believed to.be necessary to the -a safety.of the plant prior to operation at power with the reactor head.in place.. .s. q A mh 1 n The license further provides, by Section 3, for certain M*Po,rtingtend_,recordpeping gqu,grementsppay,ticularly v$th'gr - g_ g,, mm.3gd - vv' - a, y + n, m, : g,. 4 respect, to3theychange procedure'l containedjin., subsection 3 B.A .x, t,- n x., ~. This, 'lchange, per>e* "' Nadopted,aftagth.e proyietou &;q p MA; bus /Q gig.,,. % cur *,wtJ. @ g,. 6 ing f 4ch,s =-]veverp',,1s.to,be M,? a0 as one ' substantial. modifica, tion,;the provision respect 3 =, N) I - ~. W J tt W 4 S; +
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.hVlgs ? t ing ) g,. definition of,the term "facgity'), as.use4, in Section 3
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.. g #6 TJ L. .t a. 1]/4The#e' numeration'of compone$ls ditd$T'dsfin[tiion of;" facility" t represents an initial endeavor to assist in the determination of authorise'd 'changs'pr66eddrisW4"N"*W' M " *" i nc.,:
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h ') . support of the modification was that the definition includes 1b/ all of the plant systems and componcEs which have any signif-icant bearing on the safety of the reactor. The Staff expressed the belief that. there is no credible possibility that changes in plant systems outside of the definition would significantly affect the safety of the reactor. The principal effect of the y{ definition will be to eliminate reporting requirements for clianges in those portions of the plant which are unrelated to % nuclear safety. .p, in addition to all of the foregoing, constituting findings, x&W and conclusions, and based upon' the entire record of this' pro "M" s wu p ceeding, ideluding'the contentions and statements of partici-h 6 m.y A m pants and the proposed findings and conclusions which have beenQ,g. J J,,gg. -)iig$g
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wi 16.,(; The definition of '.' facility" includes the _ containment,vess'gn el'ivhich houses the reactor, ' steam generator, main coolant system, et' f;1the c ,,,l's'tNe'tiure"and normal'op5rati'i60instrumentiatlEn%d
- dt Dd#,h the main coolant loop, including piping,etc.; the pressure contro elief system, etc.;' tho chare * ~ system consisting (of high'prjylw w ps, etc.; 'the- # "-
um consisting of heat 'exchan '4 m.3 Aemical.a M a1eocue - 'ng of steam' heated i v. un u *. ' aure end iow pressure sampling and leak det
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m.. c. 3 solms and icek dercetion 6. ' consist *.soi utg'tihbt? down cooling system, etc.; safety injection system, etc.; stati6iiE, service electricali system,3 etc.;iradioactive -waste.disposaljfacilftygk ;.- etc.; radiation monitoring. system; etc.; shielding' inside andj(insmediately outside containment vessel;'etc.; fuel handling system,.etc.g sAcbudary ~ coolant' system inside containment vessels, etc.;. component. coolant. system,etc.; storage'vell: system,' etc.; cooling,: heating;f an'd(vejtila-Y ' tion systemsi etc., etc.; the unit No. 2 turbine, and maint condansere i used for steam from the facility, etc.; spent fuel storage rack,"" bej adewin;thisjfacility. - *etc.m The license providea that,no change may m s s as defined, if it involves an 'unreviewed safety que'stion",~or ~ change in technical specifications.without Coumission consideration.3 0 0
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l i l 29 adopted, anodified, or rejected, as shown herein, it is further found and concluded as follows: 1. Saxton Nuclear Experimental Corporation, a duly organised, non profit corporation existing under and pursuant to the laws of the Commotwealth of Pennsy'ivania, is the holder of Construction Permit No. CpRR-6, dated February 11, 1960, authorizing construction of a light water imoderated and cooled pressurized reactor at the.8axton Station of the Pennsylvania Electric Company situated approximately 20 miles south'ea'at of Altoona, Penni Ivania. 2. Saxton has submitted the tecIhnical information omitted from and required to complet's its app 1' cation for a i provis'ional operating lice'nie. 3. Conatruction 'of the '8'ax' ton facility has. proceeded, and N there is reaso'nable assurance that 'the ' facility will be ' completed. in conformity with(the construction permit
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,g and the application, at Sd6de'd, 'the provisions of the ^ la anietiddd, 'and the Rulm Atomic Eno t mlap# 6egulations of the Conuitosits. s, \\Q 4. There is reasonable assurance that the activities m s%
- e authorized by the provisi'oriil" operating license here-inaf ter ordered can be con' ucted without endangering d
the health and' safety of the"p6blie.. 'and that such ,, activities will be conducted in cotopliance with the Atomic Energy Act of'1954. 'as ' amended, and the Rules ,,,,and Regulations 'of the Commission. ,,n.. ...e, ,3 n '. ' di ', l
) y) S. Saxton is technically and financially qualified to engage in the activities specified by the provisional operating license hereinaf ter ordered in accordance with the Rules and Regulations of the Commission. 6. Saxton has furnished to the Commission proof of financial protection in accordance with 10 CFR, Part 140 " Financial Protection Requirements and indemnity Agreeinents". 7. There is rcasonable assurance that the Saxton facility will be ready for initial loading with nuclear fuel within ninety 190) days from the date of issuance of the provisional operating license. 8. Issuance of a provisional operating license to operate the Saxton facility under the terms and conditions here-inaf ter authorized will not be inimical to the connon defense and security or to the health and safety of the. public. WHEREF0aE, subject to review by the Counission either upon a m tion, IT IS ORDERED thatt ed* ion for certiorari or.t m # ,,9%,:. Vvisk af Lietaarug anc Pep.' '% 'shall isr 1 g to Guxton Huclear Experimencal corporation a provisional operatink licens's pursuant to 10 CFR, Part 50.57 authorizing operation of the Saxton facility, s. ? said license, inclie tng technical specifications, to be in subotance and, form as subruitted,in,,, l
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1 31 this proceeding and identified as Saxton's Exhibit No. 3, as modified by Saxton's Exhibit No. 4. 2. In accordance with 10 CFR, Part 50.57(e) this Inter-mediate' Decision and Order shall become ef fective imediately upon issuance, subject to (1) the review thereof and further decision by the Com-mission upon a petition to review filed by any party within twenty (20) days after the date hereof, pursuant to the Comission's Rules of Practice, and (2) such further order as the Comission may enter upon such petition to review or upon its own motion.u A; within forty-five (45) days af ter the date herSof; provided, however, that in the absence of any further Comission order pursuant to the foregoing, this e ld,. Ictermediate Decision shall become the final decision L of the Comission at the and of such 45-day period..,; p. age..qy-c,y . gpy-Samuel W. Je..o ? - Pecniding Officer , LQgig c O Issued: i.-,
- ",2 October'll, 1961 Gmantown, Maryland
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