ML20195E222
| ML20195E222 | |
| Person / Time | |
|---|---|
| Site: | University of New Mexico |
| Issue date: | 07/31/1984 |
| From: | NEW MEXICO, UNIV. OF, ALBUQUERQUE, NM |
| To: | |
| Shared Package | |
| ML20195E200 | List: |
| References | |
| PROC-840731, NUDOCS 8606050231 | |
| Download: ML20195E222 (180) | |
Text
.
AGN-201M REACTOR OPERATION AND OPERATOR TRAINING l1ANUAL 1
DEPARTNENT OF CHEMICAL AND NUCLEAR ENGINEERING THE UNIVERSITY OF f(EW MEXICO ALBUQUERQUE, NEW MEXICO 87131 REVISION: JULY 1984 8606050231 860602 FDR ADOCK 05000252 P PDR
TABLE OF C0!!TE!!TS Page I n trod uc ti o n . . . . . . . . . . . . . . . . . . . . . . . . . I-1 I) General Design Features . . . . . . . . . . . . . . .I-1 A) Reactor Descri ption. . . . . . . . . . . . . . . .I-1
- 8) S'tandard Loadi ng s. . . . . . . . . . . . . . . . . I-8 C) Reactor Control . . . . . . . . . . . . . . . . . .I-10
- 0) Instrumentation and Safety Systems . . . . . . . .I-17
- 1) Nuclear Instrumentation. . . . . . . . . . . .I-17 a) Channel 1. . . . . . . . . . . . .~ . . . . I-17 b) Channel 2. . . . . . . . . . . . . . . . .I-17 c) Cha n nel 3. . . . . . . . '. . . . . . . . . I-17 d) Auxiliary Channel . . . . . . . . . . . . .I-18 e) Strip Chart Recorder . . . . . . . . . . . I-18
- 2) Sa fe ty I n te rl o c k s . . . . . . . . . . . . . . . I-18
- 3) Radiation Monitoring Equipment . . . . . . . .I-18 a) Equipment List . . . . . . . . . . . . . .I-19 II) Admi ni s tra ti on . . . . . . . . . . . . . . . . . . . . I I-1 A) Administrative Organization. . . . . . . . . . . .II-1 Appendix II Administrative Command Listing. . . . . .II III) Operating Procedures . . . . . . . . . . . . . . . . .III-1 A) General Operating Rules. . . . . . . . . . . . . .III-1
- 8) Routine, lionroutine Operation. . . . . . . . . . .III-3 C) Requests for Reactor Operation . . . . . . . . . .III-5 D) Detailed Operational Procedures. . . . . . . . . .III-5
- 1) Operational ,Information. . . . . . . . . . . .III-6
- 2) Pre-start-up Check-out Procedures. . . . . . .III-7 '
3 ). Start-up Procedure . . . . . . . . . . . . . . III-13
- 4) Procedures During Operation at Power . . . . .III-16
- 5) Shut-down Procedures . . . . . . . . . . . . .III-17 E) 1) Miscellaneous Information. . . . . . . . . . .III-20
+
- 2) Power Calibration. . . . . . . . . . . . . . .III-20
- 3) Reactivity Changes . . . . . . . . . . . . . .III-20 Appendix III.A Request for Use Forms. . . . . . . . .III-21 III.8 Operations Log . . . . . . . . . . . .III-23 III.C Standard Loadings. . . . . . . . . . .III-25
TABt.E OF CONTENTS (continued)
Page IV) Maintenance and Inspections. . . . . . . . . . . . . .IV-1 A) Monthly Reactor Inspections. . . . . . . . . . . .IV-1 .
B) Semiannual and Annual Reactor Maintenance. . . . .IV-5 Appendix IV Monthly Reactor Inspection Fonk . , . . .IV . A V) Emergency Procedures . . . . . . . . . . . . . . . . .V-1 VI) Technical Specifications . . . . . . . . . . . . . . .VI-l Sections VII, VIII, and IX are available as a separate study guide.
VII) Nuclear Reactor VIII) Health Physics IX) Review Questions e
0 0
e 6
- - - - - - - - - - ,, - . . - . .,_, _ . .. ,, - ,-- - - - - - . - . - - - - - . . --- - - , - , . - - ~ - - - -
Introduction .
This manual pertains to the operation of the AGN-201M Reactor (License #R-102, NRC dqcket #50-252) at the University of New Mexico, Albuquerque, New Mexico. The reactor, a 5 watt maximum power facility, is housed in the Nuclear Engineering Laboratory Building of the College of Engineering. Administrative control of the facility resides with the Department of Chemical and Nuclear Engineering. Specific details of that administration are discussed in this document. This manual serves to provide general reactor operation information as well as Training Information for Operators. ,,
Section I General Design Features of the Reactor A) Reactor Description The AGN reactor is a homogeneous thermal reactor which is used for teaching and training. Figure 1 is a simple schematic of the reactor. Figure 2 gives rather more detail. Figure 3
, shows the core tank and its contents. The reactor cannot be operated if the temperature is <18*C.
The reactor core is 25.6 cm diameter x 24 cm high. It consists of nine fuel discs which are separated at the midplane by a thin aluminum baffle. A 1 in, diameter glory hole passes through the center of the core.
The fuel is 20 percent enriched UO2 powder embedded in radiation stabilized polyethylene. The polyethylene acts as the moderator.
! Full details of the fuel are given in Table 1. Total fuel l
loading including the fuel rods is 667 g of U-235.
There is a space at the top of the core for expansion and fission product gas accumulation.
The core fuse is a polystyrene plug which supports the
- bottom half of the core. If the temperature reaches approximate-ly 100*C, the fuse 'will melt e.nd the lower three fuel discs will -
fall =4 in., shutting the reactor down. Fuse operation is as i
I-1
M Water tank Reactor tank Core tank Lead g ,
Graphit
~\ A
- Core '
/ ccess ports Ionization chamber (linear)
, Ionization .chambe (log) (ch. 2)
O (ch. 3)
Fission chamber (ch.1) -,
!::::k Manhole cover G, lory hole Figure 1. Schematic of the reactor (looking from above).
I-2
z 6.5 ft .
~-
Manhole _ _
n 55 cm Water ~ "
~Z_- Z _ ~~~"" .
Thermal Column Tank x _N ~ _
Shield -N- ------
\_ - or Water Tank C.-.~. - - / '///////////////ll ~ -. f 10 cm Lead N N L Core Shield ~ ~
' N
/ ~ 25 cm x 25 cm h'/) n /ns / Cylinder
'----- - - - ^
% e i
Glory Hole i[ s N' ' v///j . - _ -.
[s'y /f g 20 cm Graphite 1 in. diam. . - . - -
/ -
s b -
sh Reflector access ports . -
~ ~
~// { /fff
~
n---
-- x s ; _ __}_ .
\ - ___ -
_ ~ - s N _
7 T - - - - -- Control Rods
-- - _-_ - ~ ~ - -
M- ~ - - /-
- 9.5 ft ,
Base .
Controlled Access Area !
' m e
Figure 2. AGN Model 201 M Reactor.
I-3
, cch ran a>ER
,p. .n ,. n m.m. . %. . _.3...
~
'{!,0,' '
- $'{, ,N/f s ,
$f.. ,,',,',i / /, i,/,., ',f. , f. . ,,//,/
,- i GRAPH /Ti~ n:~: nECTOR A
N.~ ' ,/,s,/ //,/,/,'i , ' /,, / < '/ ,/ ,/ // llqA
$'i/// i /'/ ,',' ,</ // f /, /,i/'///,.y
$;'/,,<
ii , i , ,
,, . / ,/. ,~,~
', jn ciscs pJ//,/.,'jj,,f, r.',,'/'//,
7 llll,f l/,.f/,, ',. '/,r,'. .x
- M
~'
'en.wvensww ,w #*-
- ist'.
- m'r&%w s,74744 gggy ggy;
.Ws'N%'t, AN '.%Mb'E
- t- \ \!(r'PN4ff/4A l (i%ER . <
i , .
'6 " l w t,9 ; 2l"*
' i%GM
. ('h f - 'S
?
~
?D? k%* h' cone rAxx h
[. - -
l'h!'N
.s , ,
,.,s.,..
,s-p, . ,
,,.3
, s ' -3,
_ , ,. - s , s, CONTROL LEAi i f
' . . I' l, E','~ y - , l' ,' RCD 7W/MELES n i Y ' N OF.~.Suf=0RTAss~.M.
! f1 l
- ..Q.
< V u.
l n u +
t <
si.
my, n --~-.. m -
~ 77f. I .. .
E 9 l > n CCRETANNCCVER E i [ ln
- b D f, :
G Figure 3. AGN-201M Cora Tank and Contents.
I-4
- - _ - . - - , . . , - - - . - . . . _ , .-- - - -- , - .,-,n.,, .- ,--- , ..~ . - - - ,--
1 l
l NUCLEAR ENGINEERING UNIVERSITY OF NEW MEXICO TABLE 1. AGN-201 FUEL LOADING Total Mass U-235 Mass Fuel Piece (cm) (gm)
Disk 20497 2150.0 . 98.89 Disk 20498 4 cm x 25.6 dia. 2158.5 99.12 Disk 20499 2026.5 93.17 -
Disk 204100 2052.0 94.39 Disk 204101 1262.5 58.01 Disk 204102 2 cm x 25.6 cm dia. 1263.5 58.07 Disk 204103 1263.0 58.05 Disk 204104 1 cm x 25.6 cm dia. 670.0 30.80 .
Disk 204105 743.5 29.76' i
Core ?use ,5.86 0.41 Fixed Fuel Subtotal - 620.67 Safety #1 315.77 14.51 Safety #2 315.53 14.50 235 315.58 14.51 Coarse Rod 0.627 gm U /cm Fine Rod 0.112 gm U 235 /cm 58.95 2.71
{ loveable Fuel Subtotal - 46.23 Total Loaded Fuel - 666.90 g I .
Disc 20497 is the bottom disc in the core, Disc 204105 is the top disc in the core as shown in Figure 4.
The approximate critical mass is 665 g U-235.
The excess reactivity at 18*C with the glory hole empty is 0.25 percent, AK/K. .
I-5
M-- _ m - -. A -. -,
AGN-201 FUEL LOADING I 7 None _ _ _ _Non _e q 8
L 204105 L
l 204104 j .
l v _ _ __ 204103 _ _ _ _ _
204102 I 204101 ,
9 9
204100 A
V .
20499 20498 1
i 20497 l
l Figure 4.' AGN-201 Fuel Loading.
l l
! 1 1
a l I-6 , i l 1
follows. There is a higher fuel loading (2 x fuel density) in ,
the fuse so during operation more heat is generated in the fuse than in the core. The temperature in the fuse rises about twice as fast as the temperature in the core.
The core is contained in a gas-tight aluminum cylindrical tank (32.2 cm diameter x 76 cm high). The core tank can be considered to consist of an upper and lower section separated by an aluminum disc or baffle.
The reflector consists of graphite on all sides of the core. It is 20 cm thick, density 1.75 g/cm3 . Part of the graphite is in the core tank and part outside. Therg are four, 10 cm diameter, access holes which pass through the graphite outside the core can.
The graphite is surrounded by a 10 cm thick lead shield.
The shielding, reflector and core are enclosed and supported by a thick steel reactor tank (47.5 cm radius). The removable thermal column tank is provided to permit access to the core tank. This is normally filled with water to provide biological shielding.
It can be filled with graphite if a thermal column is desired.
The steel tank acts as secondary containment for the core tank and is fluid tight. No experiments are allowed in the core tank. The control and safety rods enter through the bottom of the reactor tank.
The water tank is the third and outermost of the fluid tight con tainers. It is 6-1/2 feet in diameter and made of steel. It holds 1000 gallons of water and forms the fast neutron shield.
Finally, there i,s a 60 cm concrete shield in front of the ,
reactor tank--and 40 cm on the sides and back. There is no shielding on the top of the reactor tank.
I-7
The four,10 cm diameter access ports are loaded as f.ollows:
< 40 cm > < 10 cm > < -70 cm >
Wood Lead Graphi te Lead Wood The reactivity worths are:. Wood slug = 0.0027%
10 cm lead - 0.019%
20 cm graphite = 0.21%
The access ports are labelled on the reactor:
3 1 1 3 ,
N S' Face Face 4 2 2 4 The 2 Ci Pu-Be source and source drive are mounted in access port #2 on the North Face. The source drive is shown in Figure 5.
The auxiliary ionization chamber is mounted in access port
- 4 on the South Face.
B) Standard Loadings The following standard loadings are defined. These loadings comply with the requirement that the excess reactivity with the standard loading does not exceed 0.25 percent with no experiments in the reactor and the control and safety rods fully inserted. ,
Standard Loading #1 The glory hole is empty, all access port fillers are in their normal positions, and the fine control rod contains polyethylene rod sections.
Standard Loading #2 The glory hole is empty, half of the access port fillers in port 4 are removed (C, Pb, and wood) and a boron-lined ion cham-ber is fully inserted into 'the remaining cavity. The rest of the I-8
- 82.5 ca c.
Y s
~
Al Liner 3 ater * '"'
{ [ WTank Wall (3 cm ID) 14.5 cra - - -
5 cm 28 cm :
\\\\ \\\\\\-
!ffff[f . .
Cadmium Wrapped Paraffin '/.. / //
ntenna g9 j f Source Can _
1(
L 4
/'h//ihl/////h a g gxwwwus%mwwa h\' .
/
6 6 % 9 % M : '3 Wood -
W od j Antenna = 28 cm =
\
llountin/
g 3 "00T" Total Source Travel "IN" Bracket i Limit Switcl i Limit Switch
- Access Port 2 s .
""U -
PuBe SOURCE DRIVE ASSEMBLY
= 17.1 cm u l: 13.3 cm
. Antenna W"" ' '
[Q Lucite Plug 2, Ci g q_]
3 cm 1111111111111111111111111111111111111111I11111111111111111111 1,'
--- 5 . 7 cm -+
Aluminum Source Can
~2 x 106 n/sec Figure 5 PuBe Source can Detail; PuBe Source Drive Assembly.
e
cavity is then filled with paraffin or polyethylene and the access port is sealed and locked. The fine control rod contains normal fuel material rod sections.
Standard Loading #2 ( Amended)
This is the same as Standard Loading #2 except that the 2Ci Pu-Be source and source drive are mounted in the northside of access port 2.
C) Reactor Control The AGN-201 reactor has two safety rods, a coarse control rod and a fine control rod. Reactivity increases as these rods
~~
are inserted.
Two Safety Rods #1, #2 These are 5 cm in diameter, and contain 14.5 g of U-235 in polyethylene. The active length of the rod is 15 cm. The active fuel is doubly encapsulated in two aluminum containers. This isolates the fuel in the rods from the core. The total travel is 24 cm. The insertion time is 40 to 50 sec full length. The scram removal time is approximately 200 msec. The total reactivity is 1.25 percent Ak/k per rod.
- Coarse Rod This is 5 cm in diameter and again travels 24 cm. The active length is 15 cm. It can be inserted at high or low speed. It contains 14.5 g U-235 in polyethylene, again doubly -
contained in aluminum. Normal insertion / withdrawal time (high) speed is 40 to 50 secs. The slow speed insertion time is approximately twice the fast speed insertion time. Scram time is
=200 msec. The reactivity worth is of the order of 1.25% aK/K.
The safety rods and the coarse rod are magnetically coupled to a carriage and they compress a spring in fully inserted posi-ti on. Thus the removal of the electromagnet current results in the withdrawal of the rod by gravity with an assist from the compressed spring.
I-10 t
4
The rod carriages are mechanically driven to full out position following a reactor scram.
Fine Rod This is mechanically coupled to the carriage. It contains 2.71 g of U-235 in polyethylene, again doubly contained. It travels 24 cm and is 2.5 cm in diameter. It can be inserted at high or low speeds. Normal insertion / withdrawal time is 40 to 50 sec (high speed). The slow insertion time is approximately twice the fast insertion time. The fine rod does not scram.
Total worth of the fine rod is -0.25 percent ak/k.
Small adjustments of the excess reactivity of the reactor can be made by adjusting the control rod travel. This is done by altering the position of the top limit switches. This is done to ensure that the excess reactivity <0.25 percent with no experi-ments in the reactor at the minimum operating temperature. The rods are inserted in the sequence of Safety Rod 1; Safety Rod 2; Coarse and Fine Rods together or separately.
~
Figure 6 shows the control rod mechanism. A scram opens the holding magnets on the safety and coarse rods so that these fall under gravity, assisted by compressed springs, to a full-out safe posi tion. A warning light and, bell indicate that this has happened. A more detailed view of the rod drive mechanism is shown in Figure 7. The coarse rod reactivity calibration curve is shown in Figure 8. Figure 9 shows the partial fine rod cali- .
bration curve, Figure 8b shows the partial coarse rod calibra-tion.
Rod In-Rod Out The rod-in red light, rod-out green light and the rod-engaged yellow light'are activated by micro-switches.
The safety systems are " fail safe". A scram signal or power failure will de-energize the holding magnet allowing the safety and coarse control rods to be accelerated downwards and out of the core by gravity and spring loading.
I i
.- i i ;
I ,
\ D CORE j
a / .
b* CAPSULE -
_./
l I
I n .
. i e .
'_ _ L. I m i l
l SEARING MAGNET :
'Wi l l
, LE AD SCREW '-- ,
si ,
IX , ,)
\ d -
rL DASH POT I,
'/
/
CHAIN DRIVE .
MOTOR
'Tr"itY ~r'r. T_
SYNCHROS .3
~ .
Figure 6. Control Rod.
I-12 .
e
yFuel Rod Screws in at this Point Control Rod Guide Tube II 6I Ei ii I 1
= - . yy3 Upper Limit Switch D
( h 155 7Set Point
<- - - l e
._ .- j~ a,
. s .__.,,
~ b-='* l 1
Driven Lead C '
Screw l -' *j Stationary Lead Screw
'- > (Does not turn)
.- - cp c-
~"
c-
~
l 1
,\I- -$
= - . - -' Ig l i l l C)
-fUpper Limit Switch l I I '
'" l l i1 - - - -
cs I!
II 1 I I
I Ill Ie I Z;; Traveling Magnet - -
' / '-- -~
5 l ._. . . - , Rod .
'-- - l Engaged
'-~~~
', Limit '.~-$
- Coupling Length
<- >, Switch
. 8
- ' a-a '
. a-d % P hScram Spring Scram Spring 4C; -
l __._.
c-
~~~ k- lC Not Shown Two additional traveling E
l magnet guide rods
)Ch Synchro generator (chain
, f Q driven by de motor)
F2 .
Lower limit switch (rod outswitch)
I I 11 11 I i ei ll , . , ,,
N LJ L Chain Driver Dash- O Gear pot de Motor Figure 7. Rod Drive Mechanism.
1-13
4 180 -
160 -
t
. 1 40 .
120 . .
. m Feb. 9,1982 l
i
{=
v
, x 100 -
ea 5
U u .
80 - .
60 -
- From AGN (1 40 - X Tros red drop (MCA) f 20 .
0 6 e s
,0 to r 20 24 Position (cm)
Figure 8. Coarse Control Rod Calibration Curve.
I-14
~
25 -
~
Feb. 9,1982 -
Fine Rod Fully in 20 - .
200C Critical at 20.4 cm B
5 3 -
y 15 -
I 3
- e . .
, ,r-
{ 10 - / -
~
? / '
. / .
~
5_ / -
- / .
. /
/ 4 i i i 20 d 21 22 23 24
. Coarse Rod Position (cas)
Critical Figure Sb. Coarse Rod Partial Calibration.
I-15
- 1 l l I' ,l1 l, l4illl1 l
- .l 11 i.
- 4 2
d n _
a i2 2 e s
r a'
o c
( .
)
- - ed ve
- ) rt i0 m ur 2
c ce
( s nn n oi i
o i t y t al r rl e bu s if n l as I
- i8 Cd 1 !
i o
C d r F . t o y ,
s t
- ee nf ia Fs i6 9
1 e
r ug i
F
=
~
- i4 1
f - 1 2
0 0 '0 0 1 3 2 g
,u&ceU ># > IIoMe:a ,et eaa~ n s
i 6
eb f
~
m,.a, k
?
ll1 l'
The sequence of SR1, SR2 is required by the drive circuitry. The coarse control rod cannot be driven in until both SR1 and SR2 are fully inserted.
D) Instrumentation and Safety Systems
- 1) Nuclear Instrumentation a) Channel 1 - U-235 Fission Chamber
! This detector is a source-range detector of neu-tron flux used as a start-up monitor. The electron-
, ics consist of an ORTEC 109PC preamp, an 0RTEC 485 amplifier, and an ORTEC Discriminator-Scaler. The signal is generated by a gas-filled U-235 fission chamber which is biased to appr'oximately +250 Y for operation as an ionization chamber. The high vol-tage on the chamber is automatically switched off when the signal from Channel 2 exceeds 10-9 amps :
in order to prolong the life of the detector.
b) Channel 2 - Boron-lined Ionization Chamber l
Proper operation of Channel 2 is a license requirement. It provides both log picoammeter and period meter responses. The detector consists of a l positively-biased (-600 volts) boron-lined, gas-filled ionization chamber. The log picoammeter and period meter are used to assure operation within power (<2x licensed full power (5 watts) and period -
(t > 5 sec) limits). A low current (I $ 2 x 10-12 amp) scram on this channel assures detector opera-tion over the entire source to full power range of
\ operation of the AGN.
c) Channel 3 - Baron-lined Ionization Chamber Similar in construction to the Channel 2 detec-tor, this channel includes a linear picoammeter as a ,
I-17 l
l l
l
monitor of the detector current and has scrams at 5 and 95 percent of indicated range (as well as at 2x licensed full-power). .The detector is physically closer to the position of the start up source, therefore it is used to verify insertion of that source.
d) Auxiliary Channel - Boron-lined Ionization Chamber Similar to Channel 2 and 3 detectors, this chan-nel is an auxiliary monitor which can be used for highly accurate reactivity insertion measurements.
This process is accomplished by. adding a series cur-rent source (from the installed current supply) to cancel the detector signal. This differential mea-surement allows current changes to be recorded with two orders of magnitude better resolution than from the detector alone.
e) Strip Chart Recorder A strip chart recorder is used to continuously record tae output of channel 2 and either channel 3 or the auxiliary channel . Provision is made at the front of the console to select the output of either channel 3 or the auxiliary channel for recording.
- 2) Safety Interlocks There are three safety interlocks included in the ,
reactor instrumentation. If any of the three is tripped, a light is activated on the control panel and magnet current to the rod drives is deactivated (scrammed condition). Those interlocks are as follows:
I-18
a) Shield water level monitor - float-type monitor, trips if water level is more than 6 in, below the top of the tank.
b) Shield tank temperature - thermostat trips if water tank temperature drops belc.s IS*C.
c) Earthquake switch - a small stainless steel ball is dislocated by heavy vibration causing the tripped condition.
- 3) Radiatien. Monitoring Eauipment Radiation monitoring instrumentation available to the reactor operator includes a console-mounted meter and a portable survey meter. These and other such 1
instruments available within the reactor laboratory are calibrated periodically by the Radiological Safety Office of the University. There are remote area monitors with automatic alarms installed to monitor the Reactor Room, the building exhaust stack, the Co-60 cell area and the Co-60 console area. All of this instrumentation is listed below:
a) Equipment List REMOTE AREA M0llITOR (RAM) MOD RMSII EBERLIllE Remote Detector:
l 1. Ventilation stack 0-10,000 MR/HR - Alarm 10MR/HR .
- 2. Reactor room 0-10,000 MR/HR - Alarm 10MR/HR l 3. Co 60 Console Area 0-10,000 lR/HR - Alarm 10MR/HR
- 4. Coso Cell 0-1000 R/HR - Alarm 100R/HR All detectors with the exception of the one in the l
Co-60 cell are G-M type--the Co-60 cell detector is an ion chamber. All detectors can be checked by remotely activating shutters that uncover installed l check sources (Csl37). ,
l .
I-19 l
The detectors are moni.tored at the Co-60 control console. Alarm set points are adjustable.
Radiation Monitor RM-14 Eberline Detector--This is a Geiger counter for beta, gamma, or alpha radiation detection.
Range: 0-50,000 CPM Power: 115 VAC Application: This is installed in the reactor con-sole for local monitoring.
Model E 400 Eberline Detector: G.M. Beta, Gamma low Range Range: 0-200 MR/HR Applications: Primary use, monitor reactor during start up and operation. Secondary use: lab survey meter Model PNC-4 Neutron Counter Eberline Detector: BF3 detecter moderator for fast neutrons is 1-1/4 in, parafin wax enclosed in 0.03 in. cadmium. Reads thermal nuetrons when detector is out of the.well. Reads fast neutrons when housed in moderated well.
Range: 0-5000,000 CPM Application: Reactor monitor - lab survey meter e
I-20
Section II Administration A) Administrative Organization The safe operation of the AGN-201M reactor facility is assured by using well-trained operators and supervisors, following strict administrative controls. The administrative organization is shown in Figure 10 and a brief description of the responsibilities of each membe,r of the facility operations staff follows.
President of the University Committee on Radiological Control Dean, College of Engineering I
. Reactor Administrator Radiological Reactor Safeguards Safety Officer Advisory Committee
- J Chief Reactor __
Supervisor
__ Reactor Operations Committee
. Reactor __
Supervisors i
Reactor Operators __
Reactor I Assistants Authorized Operators ,
Figure 10 II-1
- - =
a) Reactor Administrator Provides final policy decisions on all phases of reactor operation and regulations for the facility. He is advised on matters concerning personnel health and safety by the Radiologi-cal Control Officer and/or the Committee on Radiological Control . He is advised on matters concerning safe operation of the reactor by the Reactor Operations Committee and/or the 4
Reactor Safeguards Advisory Committee. He designates Reactor Supervisors and names the Chief Reactor Supervisor. He approves all regulations. instructions and procedures governing facility operation. He submits the annual report to NRC. He issues and changes the code on the cipher locks of the Nuclear Engineering Laboratory Building at the beginning of each semester.
b) Radiological Safety Officer Normally represents the Committee on Radiological Control in matters concerning the radiological safety aspects of reactor operation. .He is available for advice and assistance on radiolo-
, gical safety problems. He is the emergency director if an emergency involves radiation safety.
c) Reactor Safeguards Advisory Committee Reviews and evaluates reactor operations and procedures to ensure that the reactor shall be operated in a safe and competent manner. At least two members of the RSAC are from organizations outside the University. The committee is available for advice and assistance on reactor operation problems. They must approve .
any major change in the facility. They meet at least once each senester (winter, spring). They review the physical security plan bi-annually. .
d) Reactor Operations Committee Consists of the Reactor Supervisors with the Chief Reactor Supervisor. Other qualified persons may also be members. They are directly responsible to the Reactor Administrator for the preparation and submission of detailed procedures, regulations, II-2 i
i 4
forms, and rules to ensure the maintenance, safe operation, com-petent use and security of the facility. The Committee ensures that all the activities, experiments, and maintenance involving the facility are properly logged and are in accordance with established local and U.S. Nuclear Regulatory Commission regula-tions. They evaluate all proposed changes in procedure or changes in the facility and must approve any minor change before l
the change is implemented.
Chief Reactor Superv4sor Holds a senior operator's license issued by the NRC. He is -
responsible for the distribution and enforcement of
- rules, regu-1ations and procedures concerning operation'of the facility. He l
has the authority to authorize any experiments or procedures which have received appropriate prior approval by the Reactor Operations Committee, the Reactor Safeguards Advisory Committee .
and/or the Committee on Radiological . Control (or the Radiological ,
Safety Officer) and have recetyed prior authorization by the I
Reactor Administrator. He shall not authorize any proposed changes in the facility or in procedure until appropriate evalua-tion and approval has been made by the Reactor Operations Commit-tee or the Reactor Safeguards Advisory Committee and authoriza-tion given by the Reactor Administrator. The Chief Reactor Supervisor is directly responsible for enforcing operating proce-dures and ensuring that the facility is operated in a safe, ccm-petent and authorized manner. He is directly responsible for all
- prescribed logs and records. He is the emergency director for emergencies not involving radiation.
Reactor Supervisors 3 hall hold valid senior operator's licenses issued by the Nuclear Regulatory Commission. A Reactor Supervisor .shall be in charge of the facility at all times during reactor operation and must witness the start-up and intentional shut-down procedures.
II-3 i -- - - - . - _. _ _ _ _ _ _ _ _
The Reactor Supervisors are directly responsible to the Chief Reactor Supervisor. The Reactor Supervisors do not have to be present other than when the reactor is going critical or being shutdown. However, the location of the supervisor must be known to the Reactor Operator at all times during operation so that it is possible to contact him if required.
Reactor Operators Must hold a valid operator's license issued by the NRC.
They must conform to the rules, instructions and procedures for the start-up, operation, and shut-down of the reactor, including emergency procedures. Within the constraints of the.administra-tive and supervisory controls outlined above, a reactor operator
. will be in direct charge of the control console at all times that the reactor is operating. The reactor operator is required to maintain complete and accurate records of all reactor operations in the operational logs.
Authorized Operators These are individuals who are authorized by the Reactor Supervisor to operate the reactor controls and who do so with the knowledge of the Supervisor and under the direct supervision of a licensed Reactor Operator. .
Reactor Assistant These are individuals who are present during a reactor operation to provide assistance to the Operator as needed, with the exception that a Reactor Assistant does not operate the controls of the reactor. .
In an emergency they may push the Reactor Scram button.
The duties of these individuals are summarized in Table II.
l l
l II-4 l
Table 11.1. Duties Raactor Administrator a) Approves all rules and procidures regarding reactor operations b) Appoints Chief Reactor Supervisors c) Takes advice as appropriate from RSO and Reactor Safeguards Advisory Committee d) Makes policy decisions Radiological Safety Officer a) Gives advice and assists on all matters related to radiological safety b) Represents the Committee on Radiological Control c) Is emergency director in the event of an emer-gency involving a radiological hazard.
Reactor Safeguards Advisory Committee .
a) Examines logs and records to ensure reactor is being operi~ted in a safe and competent manner l
b) Must approve all changes in reactor configuration c) Approves all routine /nonroutine operations and experiments d) Gives advice and assistance as required on operational problems Chief Reactor Supervisor a) Is responsible for the safe and competent operation of the reactor; enforces rules b) Ensures all logs and records are properly kept c) Signs request for use forms which ask to use'the reactor in a enner which has the prior approval of the RSAC d) Holds a senior license e) Acts as emergency director if no radiation hazard is involved f Reactor Supervisor '
a) Holds senior license b) Is present at start up and intentional shut down i ,
Reactor Operators i a) Follows all rules and procedures b) Keeps records and log of all operations c) Holds license d) Must be present at console at all times Authorized Operator a) Operates under watchful eye of operator i
b) Has approval of Reactor Supervisor Reactor Assistant a) Does not operate b) Can push Manual Scram button in emergency II-5
APPENDIX II Listing of Personnel in UNM AGN-20lM Administrative Command May'1986 President of the University: T. Farer Associate Provost for Research: L. Cordell Committee on Radiological Control:
Gordon B. Johnson Robert K. Jones Charles A. Kelsey, Chariman Fred A. Mettler, Jr.
Robert D. Mosely Harold Southward Dean, College of Engineering: Gerald W. May Reactor Administrator: Frank L. Williams Radiological Safety Officer: Wilbur L. Tabor Reactor Safeguards Advisory Committee:
Robert M. Jefferson R. Douglas O' Dell Jon A. Reuscher Reactor Operations Committee:
Robert D. Busch John Buksa Gary W. Cooper Glen A. Whan Charles Woodstock Chief Reactor Supervisor: Robert D. Busch ~
Reactor Supervisors: Glenn A. Whan, Gary W. Cooper Reactor Operators: Charles Woodstock, John Buksa .
O II-6
Section III Operating Procedures ,
The purpose of this section is to describe the proper proce-dures for routine operation of the AGN-201M reactor. The general operating rules shall be followed by all operators.
A) General Operating Rules
- 1) Any operation of the reactor requires approval from the Chief Reactor Supervisor as indicated on a completed form " Request for Use of the AGN-201M Reactor" Appendix III A.
- 2) The console power keys when not required are held by the Chief Reactor Supervisor. They must be~ returned to the Chief Reactor Supervisor after use. The keys may not be left at the console in the absence of licensed operators or senior operators.
3). The reactor will be operated at power levels as lim-ited by the Technical Specifications.
- 4) k maximum of 0.25 percent ak/k excess reactivity may be loaded in the reactor with the glory hole empty and with access ports containing a standard loading.1
- 5) The total worth of all experiments loaded in the reactor shall not exceed 0.4 percent ak/k excess post-tive reactivity as determined at the operating tempera-ture of the reactor. .
- 6) At least two persons must be present to operate the reactor. One NRC licensed operator or senior operator must be present in the laboratory at all times during' III-1
ooeration of the reactor. A Reactor Supervisor must approve the reactor check-out and be present in the control room during start-up and intentional shut-down.
At all other timas the supervisor .must be available for contact immediately and directly, if recuired.
- 7) During operation, a licensed or authorized operator must renain at the console at all times and devote his full attention to the operation of the reactor.
- 8) The above-mentioned autho'rized operator need not be an NRC licensed operator provided he has been trained to the satisf action of the Chief Reactpr Supervisor, oper-ates the reactor only with the knowledge of a reactor supervisor, and operates the reactor under the direct supervision of a licensed operator.
- 9) No changes in the configuration of the reactor, the circuitry of the instruments and cdntrols or sc' ram-level adjustments on the scram panel may be made without explicit auth'orization of the Chief Reactor Supervisor (who needs prior approval of the Reactor Safecuards Advisory Committee). ,
- 10) No equipment or materials of any kind may be intro-duced into the reactor without explicit approval and authorization by the appropriate authority (or.authori- ,
ties).
- 11) En case of any unusual or unexpected incidents (such as instrument f ailure or. malfunction, abnormal readings, mechanica.1 problems, etc.) the reactor will be immediately scrammed, the console power key removed from the switch, and the Reactor Supervisor notified.
III-2
i
- 12) A record of all reactor operations shall be kept in the Reactor Log and approved by the Reactor Supervisor -
at the end of each operation.
- 13) When the Reactor Laboratory is to be unattended or at the end of a working day, the reactor console key shal1 be removed from the console and returned to the person authorized for its custody and, unless otherwise authorized, the Reactor Laboratory shall be locked.
- 14) Personnel radiation monitoring devices shall be worn while in the Reactor Laboratory.
B) Routine and Nonroutine Operations of UNM AGN-201 Reactor
- The limitation on the maximum allowable insertion of reac-tivity in the AGN-201 reactor is.used to decide if an experiment and/or operation is routine or nonroutine. The technical speci-
- fications of the AGN-201 allows for a maximum total insertion of
+0.65 percent reactivity to the standard core. The standard core -
consists of the fixed fuel discs 20497 through 204101 for. a total of 443.58 grams of U-235, and the removable fuel discs 204102 through 204105 'for a total of 176.68 grams of U-235 (total mass of U-235 is 620.26 grams). The control rods (coarse and fine) can amount to a maximum of +0.25 percent. There is a maximum allowable reactivity of 0.40 percent which can be inserted by the experiments.
Routine Reactor Operation of AGN-201 l
The routine reactor operation, therefore, will include the:
- 1. Operation of the reactor in its design configuration, i.e., glory hole empty, access ports containing their l design loading, thermal col *umn (water or graphite) in position with its design loading.
- 2. Operation whereby the only intentional means of changing I flux levels in the reactor is by manipulation of the con-trol rods, or by removing the source.
III-3
- 3. Operations in strict adherence to all applicable proce-dures and rules as detailed in the Manual of Operation for the AGN-201 Reacter Facility for the University of New Mexico.
The presently anticipated operations and experiments requirir.g no more than routine reactor operation are:
- 1. Reactor demonstration (non-teaching operation)
- 2. Control rod calibration
- 3. Monthly inspections
- 4. Routine operation following maintenance
- 5. Operator training
- 6. Excess reactivity determination with ,the reactor in its design configuration
- 7. In addition those experiments which are conducted as part of the Reactor Laboratory course and which have the prior approval of the Reactor Safeguards Advisory Committee are defined to be routine operations.
Nonroutine Operations All operations on the reactor which are not defined as routine are regarded as non routine. For example any operation whereby reactivity is inserted other than by moving the control rod, or neutron source, would be regarded as nonroutine (unless it comes under category 7 above).
Detailed precautionary measures will be taken prior to the performance of any such proposed cperation to ensure that (1) the .
reactivity addition' of all positive components will not exceed the 0.4 percent ak/k as specified in the technical specifications of operation license, and (2) any activation of the experiment will not result in exceeding generally licensed quantities and/or in excess exposure to personnel. Prior to the initial perform-ance of an experiment of the type described herein, estimates of reactivity worth and anticipated activitie,s are required. (Sub-sequent performance of the experime.1t can make reference tc the l l
i I
III-4 l l
l l
initial calculations and experimental results). Reactivity worth calculations will normally utilize the importance function method as discussed in Section E2. For many of the common materials the importance function is given directly in the reactor operator's logbook. For other materials the experimentally determined importance functions for each particular component process (mod-eration, scattering, absorption and fission) can be used. In some cases results of experiments on other AGN-201 reactors may be utilized, Reference 1. As usual all activities which will be produced must be estimated. Any nonroutine operation of the reactor must have the prior approval of the Reactor Safeguards Advisory Committee. (Reference 1: ANL-6900, A Manual of Reactor Laboratory Experiments, Argonne National Laboratory, Jan.1965, Experiments 10 and 11.)
C) - Requests for Reactor Operation Each operation to be performed with or on the AGN-201M must be initiated by submitting a: formal request to the Chief Reactor Supervisor. This formal request should be completely filled out and signed. Each request is reviewed by the Chief Reactor Super-visor and must possess his signature approving the operation before the ' operation can be' performed. The approval of each
. request by the Chief Reactor Supervisor will be governed accord-ing to the rules set down in accordance with those regulations established by the USNRC. The Reactor Administrator may desig-
~
nate an acting Chief Reactor Supervisor during periods of absence of the Chief Reactor Supervisor (vacation, travel, etc.).
DJ Detailed Operational Procedures
' As indicated in the general operating rules all reactor operations will'be logged in the AGN-201M reactor Operations Log. A sample operations log form is shown in Appendix III B. A description of detailed operational procedures follows. .
III-5
- 1) Operational Information .
The information which is to be entered into the tog explains the purpose for which the reactor is to be used. It indicates the Request For Use Humber, the ,
names of the licensed operator and Reactor Supervisor and any authorized changes which are necessary for the performance of the operation. The standard loading, glory hole loadings, and reactor temperature are recorded so that the supervisor may estimate the available excess reactivity. If the experiment is new the supervisor must sign the . log indicating that he is familiar with the procedures to be,.followed and approves them. The log is completed as follows:
a) Complete A-OPERATIONAL INFORMATION on the log sheet, b) Describe the experiment or operation authorized i
in sufficient detail that it can be easily identi-fied. Record the number of the approved Request For Use. Identify the standard loading in use, c) List all authorized changes to the reactor standard loading, circuitry, etc. Any unusual situation not identified as a previously authorized change is to be reported to the Supervisor immedi-ately .
d) Indicate the intended start-up glory hole load-ing and the temperature of the reactor and list any ,
additional pertinent information under remarks.
Note: If the water temperature is more than 2 degrees below previous readings, proceed with caution.
III-6
, - - , ,y _-, _ . - _ -- _ -. _._
e) Obtain the Supervisor's approval (signature) if f
the experiment is new before proceeding. ,
(
- 2) Pre-start-up Check-out Procedures At the beginning of each day's work, or whenever the reactor is being started after an appreciable shut-down time, the check-out procedure outlined in the next sec-tion.of this manual is to be completed and, when indi-cated in the log start-up check list, recorded therein.
I a) Obtain Key from Reactor Supervisor Inform the Supervisor and nearby personnel of intended reactor operation. Insure reactor tempera-ture as read on the Control Panel is greater than 18*C (do not operate reactor if temperature is less than 18'C).
PURPOSE: To alert people in Reactor Lab and ccmply i with license.
b) Check Health Physics Instruments Check Portable Gamma Survey Meter Battery Vol-tage. Check operation using low activity Cs 137 check source. Ascertain that the Area Radiation Monitor installed in Reactor Panel is on. Check operation using the Cs 137 Check Source.
PURPOSE: To insure that there are properly oper-I ating monitors available when reactor is irr use.
c) Turn on Control Panel Power. Do not continue unless alarm bell rings.
l d) Turn on power to the ' Channel 1 Instrumerit Bin, the Channel i High Voltage and the Recorder. Turn on Panel Illuminating Lights located on top of Control Panel.
PURPOSE: Sel f-evident III-7
. e) Visual Inspection a.nd Radiation Survey of the Reactor Make a radiation survey around reactor at the following locations:
(1) Reactor Access Shield Doors (ii) Glory Hole (iii) Access Ports (iv) Thermal Column Any abnormal radiation level should be reported to the Reactor Supervisor before proceeding (normal reading is less than 2 mr/hr shut down),
Ascertain that the Thermal Column and Man Hole Cover are secured and that Console Doors are closed and locked.
Make a visual check for any water leaks or other unusual conditions. Report any abnormal observa-tions to the Reactor Supervisor before proceeding.
Check that the Access Port Shield Blocks and the Reactor Shield Doors are in place. Note in Log any intended changes in the loading of the Access Ports.
Replace all chains af ter inspection.
PURPOSE: To insure that all. shielding is in place, that there is no leakage of water from Shield Tank and that everything appears normal in the core. Chain on stairwell to top of reactor has a bell which must be j secured for radiation safety monitoring. l l
l l
1 III-8
l f) Check Source Drive Check the operation of the Source Drive Unit by withdrawing and reinserting source. Note the proper operation of the Limit Switch Indications by the ,
light on the Reactor Console and observe changes in neutron level indicated by the Reactor Instrumenta-ti on.
PURPOSE: Source needed for Meter Indication at Start-up--Channel 2 Low level Trip is below Source Level--checking operation of the neutron source drive also Checks Chan-nel 2 and Channel 3 instrument and checks Period Scram and Recorder.
g) Channel 1 - U235 Fission Chamber Check Channel 1 of the Neutron Flux' Monitoring Instruments to ensure its proper operation.
(i) Check that the Start-up High Voltage Switch on the Control Console is in the Ready posj-tion.
(ii) Check and record the High Voltage on the Fission Chamber.
(iii) Check and record the Amplifier Gain and Dis-criminator Settings.
(iv) Check the Automatic Removal of High Voltage by switching Channel 2 to the HI CAL con-dition. Return to Ready Condition.
PURPOSE: To ensure that Channel,1 is operational and that the High Voltage is removed when Channel 2 reaches 10-8 amps to prolong the life of the U235 Fission Chamber.
Channel I has no Safety Trip Function and ,
'- is not required for Start-up.
- III-9
_ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ _ __________________.___a
h) Ion Chamber High Voltage Supply Channels 2 and 3 (i) To check Channel 2 Supply, depress Channel 2 Meter Switch on the Ion Chamber H.V. Supply 2
Chassis. Read and record the Meter Indica-tion.
(ii) To check Channel 3 Supply, depress and hold the Zero Switch on Channel 3 and then depress the Channel 3 Meter Switch on the Ion Chamber t
H.V. Supply Chassis. Read and record the Meter Indication. Release the Zero Check Switch.
PURPOSE: To check condition of batteries supplying ,
the Detector Voltage. Batteries are 300 VDC type. Two batteries in series for each Ion Chamber (one 300 VDC battery for AUX Channel which is not checked).
- 1) Channel 2 Instrument Check Check Channel 2 of the Neutron Flux Measuring Instruments. Channel 2, which is a Log Picoammeter and a Period Meter, receives its current from a baron-lined Ionization Chamber. The check is per-formed as followsi l
(1) Depress the check infinity switch and check that meter reads infinity.
(ii) Reset all safety trips. On Channel 2 drawer, place test switch in " Low Trip" position.
Observe that low level trip alarm light comes I
on when there is a loss of magnet current, and that an audible alarm occurs.
l 2 Multiply reading by 100 to get voltage.
III-10
. __ . ~ _ _ _ .-. _ . - - . . _ - . __ . . . - _ _ -
(iii) Reset all safety trips. On Channel 2 instru-ment drawer, place test switch in "High Tri p" . Observe the high level trip alarm light, and that the magnet current is removed, and an audible alarm occurs.
Observe also at this time that. the period
' trip alarm light is functioning.
(iv) Check calibration.by turning CAL switch to low (10-11) and to high (10-s),
(v) After completing the checks, assure that the instrument is ready to operate tiy observing
~
the Normal Source Level Signal and Chart Recorder Indications.
PURPOSE: To insure that all Trips are functioning and that Channel 2 is operating norrcally.
NOTE: On checking Safety Trips, all Trips must be reset. When Trip occurs, note loss of
- Magnet Current, Red Trip Alarm Light and Audible Alarm (Bell).
j) Channel 3 Instrument Check Check Channel 3 of the Neutron Flux Measuring Instruments. Channel 3, which is a Linear Pico-ammeter, receives its current frem a boron-lined
~
Ionization Chamber. The check is performed as follows:
. (i) Depress the Zero Check Switch with the ~
instrument en the 0.3 x 10-12 Range and adjust, if necessary, with the Zero ADJ Control .
(ii) Reset all Safety Trips and check the Low Level Scram by turning the Current Range Switch to a less sensitive range and observing that Magnet Current is removed and that the Trip condition (Reset) is indicated on the Scram Chassis.
III-11
'(iii) Reset all Safety Trips and check the High Level Scram by turning the Current Range Switch to a more sensitive range and observing that Magnet Current is removed and the Trip condition (Reset) is indicated on the Scram Chassis.
(iv) After completing the checks, assure the instrument is ready to operate by observing the Normal Source Level Signal and Chart Recorder Indications.
PURPOSE: To ensure correct operation of Ionization Chamber giving power' output, ensuring a Scram at 5 or 95 percent on any scale.
This ensures that reactor will not exeed 200 percent of 5 watts, and will not operate if this Channel is not function-ing. ,
NOTE: It is necessary for there to be an Audib1h Alarm as well as Loss of Magnet Current; and Alarm tight (keset) on all Sa fety Trips, k) Recorder Check Check Channel 2, recorder zero. Check Channel 3, recorder zero. Zero checks can be done when checking out Channels 2 and 3 instrument alarms. -
l l 1) Macnet Current Check Reset all Safety Trips and observe and record the Scram F4gnet Current. During the checks on Channel 2 and 3 the proper operation of the Low Current Trip Indicator should have been confirmed.
The High Current Trip is checked monthly.
III-12
_____ 1____________.___.__ _ _ _ _ - . .
PURPOSE: This is to ensure that the Magnet Current supply is operational and that the current is in the proper range.
m) Interlocks .
Check that the Safety Interlocks are in normal operating condition. Any of the folloMing condi-tions will cause a red light to appear on the Safety Interlock Indicator on the Scram Chassis.
(i) Shield water level low (ii) Shield Tank temperature below 18'c
~
(fif) Earthquake Switch open If any of the above conditions exist, they must be corrected before the reactor can be operated.
PURPOSE: To ensure the reactor will scram should any of conditions f), fi) or fif) exist.
n) Manual Scram Test
- Reset all Safety Trips and Drive Safety Rod Num- .
ber 1 fully in. Push the Manual Reactor Scram but-i ton. Observe that the Rod Drive Actuated Light Indicator is out and that the Rod has dropped.
PURPOSE: To ensdre that the Reactor can be scrammed before operating at power.
. o) Sie1atures ,
Start-up Checkout to be signed by Operator per-forming Check--Checkout to be reviewed and then signed by Reactor Supervisor if no problems are
! evident.
- 3) Start-up Procedure Af ter the Daily Check-out has been completed, the l
procedure for reactor start-up is as follows. Where III-13 i
indicated, information should be recorded en the log sheet.
a) Record the time of start-up and elapsed time meter reading in the log.
b) Remove cadmium from glory hole.
c) Record the background radiation level at the console from the gamma monitor or a survey meter.
d) Observe that the.0UT and ACTUATED lights are on for each of the four control rods. Reset the ROD OROP switches to the ROD ENGAGED , conditions, if required. .
e) Record the fine and coarse control rod lower limit positions.
f) Record the meter readings on Channels 1, 2 and
- 3.
g) Raise the safety rods, first number 1 and then
- number 2. . During this operation carefully watch .
the console instruments to ascertain that both the instruments and flux level are behaving normally.
h) When both safety rods are IN, as indicated by the panel lights, record the meter readings on Channels 1, 2 and 3.
NOTE: When both safeties are up, they can be run down again only by init'f ating a scram.
- 1) Compare the instrument readings with readings from the preceding reactor operation. I l
O III-14
.i) Change Channel 3 rance as sional reachGs about 80 percent of full scale and do not allow needle near the 10 or 90 percent readings on any rance.
k) The fine control rod should be partially in-serted before reaching critical with the coarse rod. Once desired power level is reached, it can then be maintained by use of the fine con-trol rod. A slow speed is available for both the coarse and fine rods for convenience in reproducing rod positions.
- 1) As the power level is oradually increased, the Channel 1 detector hioh voltage is automatically removed when a ore-selected power level is reached, unless the STARTUP HIGH VOLTAGE switch is in the BYPASSED condition. The bypass per-mits making measurements with Channel 1 at the higher power level:, if required.
, m) When it is evide'nt that the reactor is super-critical, and orior to reachino the desired power level, the startup neutrcn source may be remcved. The removal of the source should be noted in the Riactor Log.
n) When the desired steady power level 'is attained, '
.as indicated by the Channel 3 current, record the time, .the coarse and fine rod positions, and -
the output readings of Channel 2, the auxiliary channel, and Channel 1 (when applicable).
o) Che'ck the radiation levels in occupied areas of the reactor room and record the levels at the console and at check point No. 3. Also record
- the readings of the console radiation monitor.
III-15 S
e 9
i
)
- 4) Procedures Durinc Ooeration at Power i a) Routine Operation In routine operation, the reactor is, in general, l controlled by means of the fine control rod. This l is most easily done at slow speed. If it is necesssary to move the fine rod in beyond 22 cm to achieve " criticality", it should be brought back to about m'id-scale and the coarse rod inserted.
At operating power level, the linear micromicro-ammeters (Channel 3 and/or the auxiliary channel) will provide the most sensitive indications of power level. However, they should be cross-checked against Channel 2. The log is to be kept at all times during operation with power level changes, times of changes, cperator changes, glory hole
- insertions or removals, control rod positions, Channel .3 readings and other, pertinent details logged. During extended operation at a constant .
power level an entry should be made at least every fifteen minutes.
b) Chances in Reactivity:
(i) Positive--if moderator, scatterer or fuel is inserted into the reactor, or if an absorber is withdrawn, the reactivity will increase, ,
The control rod should be withdrawn, and the insertion (or withdrawal) of the materials should be made at such rates that the flux level can be maintained near1y constant.
1 e
/
III-16
NOTE: It is assumed that the effect on reac'tivity of the experiment has be'en evaluated and approved. If the flux builds up faster than the control rods can follow it, depress the REACTOR SCRAM. Do not intentionally let the flux level build up to such a level that a high-level scram will occur.
(ii) Negative--a negative change in reactivity results from the insertion of an absorber or the withdrawal of moderator, scatterer or fuel. It is not necessary to follow this change with a control rod. If, however, a constant power level is desired, the inverse of the procedure as in (i) above may be fol-lowed.
(iii) Abnormal--if a flux indicating instrument fails or malfunctions or if reactor operation
- is in any way abnormal. or if the operator has .
any serious doubts or uncertainties about the safety of continued operation, the reactor should be shut-down and the supervisor advised immediately.
- 5) Shut-down Procedures
~
a) Intentional -
The Reactor Supervisor must be present in the control room during any intentional shut-down.
There are a number of methods which can be,used to shut down the reactor. A rotation of these methods to scram the reactor intentionally serves as a safety check under operating conditions. Listed below are the methods for intentio.nal reactor shut-down.
III-17
(1) Depress manual scram buttca (ii) Shut off the control power at the console (iii) Increase the range sensitivity on Channel 3
'~~~~l for a high-level scram (iv) Decrease the range se'nsitivity on Channel .3 s for a low-level scram (v) Rod drop--the reactor can be made suberitical by dropping any one of the safety rods or coarse rods by depressing the ROD ENGAGED / ROD DROPPED switch for the appropriate rod. ,This permits a measurement of the reactivity worth ,
j of each of these rods by. the rod drop" tech-nique. Such a safety rod drop must be fol-lowedbyacompleteshut-downbeforeopera-tion can be resumed NOTE: Failure of any of these methods to scram the reactor. will require the operator to scram the reactor by another method and report'the failure immediately to the Reactor Supe'rvi-sor. The SCRAM METHOD to use on a particular day is obtained from the previous operating log and the scram sequence indicated at the reactor control console.
' The shut-down methods described are only those used under normal conditions. In event of emergency the reactor should be scrammed by depressing the REACTOR SCRAM button. In this case the nature of the emergency should be noted in the log book and reported to the Reactor Superviscr immediately. A scram from any cause will result in the low current trip indication changing from READY (green) to RESET (red). At the same time the scram magnet current
(
III-18 m - - _ _ _ _ _ _ _ _ _ .
indication will drop to zero and the rod ACTUATED lights will extinguish. All four rod carriages will immediately begin to drive downward.
The scram will be indicated by a bell alarm which may be silenced by depressing the audio alarm bypass ENGAGED / BYPASSED switch. When the rod carriages reach their lower ifmits the IN lights come on. When .the scram condition and low current trip have been reset to the SAFE or READY condi-tions, the reactor can be restarted.
b) Unintentional ,,
If an autonatic instrument. scram occurs, the same sequence of events, as just described, will occur. The origin of the scram must be determined from the change in trip indicator lights and must be recorded. Resetting of the scram condition and low current trip permits restarting of the reactor, c) Securing the Reactor In securing the reactor, the operator should wait until all rods OUT and ACTUATED Ifghts are on, then insert the reactor start-up source. Console and Channel 1 power should be turned off. The key should be removed from the switch and returned to the person authorized to keep it. All portable radiation monitors should be turned off. Cadmium
. should be inserted in the glory hole. Check that console panels and skirt doors are locked. The flux indicator instruments are normally left on with
- appropriate scale settings on Channels 2 and 3 for shut-down flux levels. Record the time of shut-down procedures in the log. The log should be signed by the authorized or assistant operator, the licensed operator, and then the supervisor.
III-19 e
E) Miscellaneous Information
- 1) Power Calibration The reactor power (nominal) will be measured annual-ly. The measurement will be made by observing the resulting activity in a gold foil af ter an hour of irradiation at I watt (nominal) at the center of the core. The activity /mg will be compared with the .
activities obtained in prior measurements of this kind.
The activity will be measured by s-counting the foil in the 4x s-counter situated in the counting laboratory.
Standard gold foil will be used for the measurements.
Nominal power is defined to be ,.the power associated
-8 with a current of 2.012 x 10 A in the Channel 3 ionization chamber. If the observed current is taken to be associated with a power of 1 watt, then the history of operating the AGN reactor show that it can be operated safely under this assumption. It is never operated above 5 watts nominal power on this basis.
- 2) Reactivity Changes Before an experiment can be performed on the AGN reactor it is necessary to estimate the likely reactiv-ity change associated with the experiment. This change will be estimated in terms of the likely change in the Fine Control Rod position (cm) at nominal operating temperature (18'C). Information is ava.ilable in the -
reactor operation log book from which these estimates can be made.
III-20
APPENDIX III.A REQUEST FOR USE OF THE UNM AGN-201 REACTOR Request No. Date
- 1. Person or Organization Requesting Use of Facility
- 2. Nature of Operation Being Requested
'~
A. Routine Reactor Operation a)
Standard Equipment b)
B. Nonroutine Reactor Operation
- 3. Description of Operation or Experiment (use additional sheets if necessary).
- 4. If Operation is nonroutine complete. the following (use additional sheets if necessary, showing any calculations):
A. Changes in Reactor Conditions B. Estimated Reactivity Worth of Changes 1
- 5. A. Isotope (s) to be Activated B. Physical State of Sample (s)
III.A-1 l
l
C. Chemical State of Sample (s)
D. Amount of Sample E. Containment During Irradiation F. Estimated Integrated Flux (nyt) Desired ,,
G. Products of Activation H. Half-lives of Products I. Activity upon Removal J. Special Handling Requirements
- 6. Date Desired Signature of Applicant This form should be returned to the Chemical and !!uclear Engineering Department Office. The applicant will be informed of the disposition of his request, and, if approved, the time scheduled for the operation. Please try to allow two veeks for processing this form and scheduling reactor time.
l 1
III.A-2
. l
,i
- 7. REVIEW 0F PROPOSED OPERATION
- 1. Reactor Supervisor
- 2. Reactor Operator
- 3. Scheduled Time for Operation (Time and Date)
- 4. Remarks, Condition, Suggestions:
Data Approved Chief Reactor Supervisor e
t e
e e
III.A-3
APPENDIX III.B THE UNIVERSITY OF NEW MEXICO PAGE AGN-201M REACTOR OPERATIONS LOG DATE OPERATIONAL INFORMATION:
Reactor Operator Reactor Supervisor Request for Use #:
Authorized Changes (loading, instruments, etc.): Standard Loading No.
Glory Hole Loading -
Water Temp. C Remarks:
Supervisor's Approval (Signature Required for New Experiments)
START-UP CHECK-0VT
- 1. Nearby Personnel Informed 10. Ion Chamber HV Supply:
- 2. Survey Heters OK -
Channel 2 HV Vol ts
- 3. Turn on Control Panel Power Channel 3 HV Vol ts DO NOT Continue Jnless Alarm 11. Instrument Check, Ch. 2:
Bell Rings Caeck Infinity
- 5. Recorder Power On Period Scram OK
- 6. Radiation Survey OK High Level Scram OK
- 7. Reactor Inspection: Calibrate 10-ll,10-o
! Thermal Column Secured 12.' Instrument Check, Ch. 3:
Manhole . Cover Secured Zero Check Access Shield Doors In Place (0.3 x 10-12 Scale)
Visual Check for Water Leaks Low Level Scram OK Stair Chain in Place High Level Scram OK
- 8. Source Drive OK Ready to Operate i
Instrut. Check Ch 1 13. Recorder OK
- 9. Detector HV Volts 14. Magnet Current Check:
Amplifier CG , FG Magnet Current ma Discriminator Level y Low Current Trip Compare Previous Operating 15. Interlocks OK Conditions 16. Manual Scram OK Automatic HV Removal OK (Raise SR 1)
Ready to Operate 17. Start-up Check Completed Operator Supervisor III.B-1 s
- I Page Date
1 Time of Startup Instrument Readings Elapsed Time Meter Reading Channel All Rods OUT Safeties IN Cd Removed from Glory Hole 1 ,
Model RM 14 Reading cpm 2 )
, Control Rod Lower Limit Positions 3 l l Fine cm, Coarse cm Previous Meter Readings Noted l CriticaT Readings .
Channel 3 Meter Reading of reached at time of day )
l Elaspsed Time; Ch. 1 cpm; Ch.2 amp !
Aux Cn. amp; Power Level watts l Radiation Level at Console mr/hr; RM 14 cpm; ;
Check Point 3 mr/hr l D. OPERATIONAL DATA .-
Ch. 3 Fine Rod Coarse Rod Remarks (loading changes, power level l
Time Reading Position Position changes, scrams, etc. -
l 1
{
t E. REACTOR SHUT-00!!N Method of Scram Time of Day Elapsed Time .
All Rods Down Startup Source in Monitors Off Recorder Off Console Power & Ch. 1 Bin & HV Off Reactor Assistant Licensed Reactor Operator Authorizea Operator Reactor Supervisor III.B-2
-- - - - , . . . - - - -n. - - - _ _ _ . - - - - - - - - - - - . - - . . - - - - - - . - , , , . , - - - ~ - - - - - - - . .
APPENDIX III.C UNM AGN-201M STANDARD LOADINGS These loadings comply with the requirement that the excess reactivity with the standard loading does not exceed +0.25 percent ak/k with no experiments in the reactor and the control and safety rods fully inserted.
STANDARD LOADING # 1 The glory hole is empty, all access port fillers are in their normal positions, and the fine control rod contains poly-ethylene rod sections.
STANDARD LOADING f 2 The glory hole is empty, half of the access port fillers in port 4 are removed (C, Pb, and wood) and a boron-lined ion cham-ber is fully inserted into the remaining cavity. The rest of the cavity is then filled with paraffin or polyethylene and the access port is sealed and locked. The fine control rod contains normal fuel material rod sections.
STANDARD LOADING #2 (Amended)
The 2Ci Pu-Be source and source drive a.e mounted in the north side of access port 2.
e 9
III.C-1
,- ~ --
Section IV Maintenance and Inspections Maintenance of the reactor equipment and components is a responsibility of the Chief Reactor Supervisor. It is also the responsibility of the reactor operator to inform a Reactor Super-visor of any maintenance which is required on the reactor. Per-iodic checks and inspections will be used to determine equipment failures and deterioration of the reactor components. When an equipment failure occurs during a check-out or reactor operation, the operator should discontinue operation and inform the Reactor Supervisor immediately. Following the Chief Reactor Supervisor's authorization, adequate steps will then be taken to correct the fault. Such maintenance will be recorded on.a Reactor Maintenance Log Sheet and approved by the Chief Reactor Supervisor.
There are various components of the AGN-201M which will require thorough inspections and maintenance periodically. A reactor maintenance log book will be kept, whose entries will.
include equipment failures and. corrective measures taken, peri-odic inspections, reactor maintenance, and any reactor modifica-tions. Each entry in the log book will possess the date of the entry and the person or persons performing the maintenance.
Listed below is a set of inspections which will be made. The frequency of these inspections is determined by the Chief Reactor Supervisor.
A) Monthly Reactor Inspections Clear all Alarm Conditions and Restore System Configuration to normal prior to proceeding from one step to the next.
- 1) Start Up H.Y. Cut Out Function With picoammeter adjusted for positive polarity apply 10-10 amp signal to Chant.'.i 2. Increase signal to 10-9 amp.
Check: H.V. to Channel 1 shuts off at 10-9 aup read on Channel 2, indicated by Power Indicator IV-1
I i
I Light of H.V.P.S. module extin'guishing. (NOTE:
Leave picoammeter installed.)
PURPOSE: Insure Channel 1 Fission Chamber protected ,
from excessive current that would occur at >10-9 amp.
i Check: High Level Scram occurs at = 1.8 x 10-7 l amp and less than 2 x 10-7 amp (200 percent of rated power). .
PURPOSE: Verify the reactor cannot be operated at a power level > 10 W (2 x rated full power).
b) Low Level Scram - Decrease Picoammeter Current until a Low Level Scram occurs.
Check: Low Level Scram occurs at = 2.5 x 10-12 amps.
PURPOSE: To verify that the reactor cannot be oper-ated if Channel 2 is inoperative.
c) Period Trip - Operate the Picoammeter Source to produce a period of 5 seconds indicated by Channel 2.
Check: Period Scram occurs when indicated period approaches 5 seconds.
PURPOSE: Verify reactor cannot be operated on a -
period of 5 seconds or less. (NOTE: Restore i Channel 2 Detector Signal Cable).
- 3) Channel 3 a) High Level Scram - Lock Channel 3 in the Meter Zero Position and feed the Picoammeter Source to l Channel #3. Unlock the Meter Zero and approach a ,
reading of 95 percent from below, on any scale.
Purpose:
To check High Level Scram initiated at meter reading of 95 percent.
IV-2
b) Low Level Scram - Lower Picoammeter Current until a Low Level Scram occurs.
Purpose:
To check Low Level Scram initiated at meter reading of 5 percent.
c) Maximum High Level Trip - Raise Picoammeter Current to 2 x 10-7 amp.
Check: Scram condition exists (cannot be cleared) for any input current greater than 2 x 10-7 amp regardless of meter scale.
PURPOSE: Assure reactor cannot be operated at power level greater than 200 percent of rated, power.
d) Highest Operating Range - Reduce Picoammeter Current to just below maximum High Level Scram Trip Point and demonstrate 0.3 x 10-6 amp to be the highest operating range.
Check: Scram condition exists (cannot be cleared) for any range selected above 0.3 x 10-8 amp scale.
This verifies reacter cannot t'a operated at excessive power levels.
- 4) Safety Interlocks a) Water Level Scram - Remove Water Tank Inspection Cover and move the float to simulate low water level in the Shield Tank, note water condition.
Check: Safety Interlock circuit changes from Reset to Trip Condition, water is clear witi, oil film.
b) Water Temperature Scram - Remove Thermocouple from stowed position below Shield Tank, immerse in ,
18'C water / ice bath.
Check: Safety Interlock circuit changes from Reset to Trip Condition.
c) Earthquake Scram - Remove ball from its position below the reactor.
IV-3 J
. Check: Safety Interlock circuit changes from Reset to Trip Condition.
PURPOSE: To insure the reactor cannot be operated if there is insufficient biological shielding, temperature less than 18'C or there is an earthquake.
- 5) Lower Rod Position, Ro; '1sertion Speed, Upper Rod Position a) NOTE: INSURE CADMIUM '.0D INSERTED IN GLORY HOLE BEFORE PROCEEDING. Note indicated rod positions when fully withdrawn. '
b) Select " Fast" speed and insert all rods in nor-mal sequence, timing each insertion.
c) Note indicated position of each rod when fully inserted.
Check: All Rod Indicator Lights signify "In" and
~
l in out (insertion time) i 1 cm/sec for each rod.
PURPOSE: Insure reactivity addition rate is less than a desired maximum.
NOTE: Leave Rods. inserted.
- 6) Manual Scram Push " Scram". button on console.
Check: All rods indicate out.
PURPOSE: Ensure Fbnual Scram Function operative.
- 7) Magnet Current (Portions Recuire 2 People) a) Initiate a Scram condition.
Check: Magnet current decreases to zero.
PURPOSE: Insure rods can be scrammed when required, b) Reset Scram condition, adjust Rm inside back of console to increase Scram magnet current until a Scram occurs. Note magnet current at which this happens.
Check: Yalue less than 90 ma.
IV-4
PURPOSE: Insure Scram magnats will not b2 damaged by overcurrent condition. .
- 8) Channel 1 Fission Chamber a) Check: Anode H.Y. = 250 V Course Gain = 8 Fine Gain = 7 Disc. Level = 0.6 Y b) Take Plateau measurement in 50 V steps from 50 to 500 Y. (NOTE: Restore H.V. to 250 V.)
c) Measure count rate with source positioned to "IN". '
PURPOSE: Verify proper operati,on of Channel 1.
- 9) Emergency Evacuation Alarm Test the alarm by activating it at the switch on the north wall by the door.
Check: Alarm sounds PURPOSE: Verify alarm available B) Semiannual and Annual Reactor Maintenance These items of reactor maintenance are those beyond the monthly maintenance schedule which are required for compli-ance .with our operating license.
- 1) Calibration of Nuclear Instrumentation. A power calibration is performed with a gold foil activation measurement to obtain correlation of detector signal with neutron flux, and hence power, for Channel 3.
- 2) The core excess reactivity and the worth of the coarse and fine control rods are measured.
- 3) The coarse rod and safety rods are removed from the reactor and checked for proper mechanical operation and limit switch adjustment.
IV-5 -
E
' ^
._ - . _ . - - - - = _ _ . - _. - . _ .
APPENDIX IV A MONTHLY REACTOR INSPECTION AGN-201M REACTOR PAGE 1 0F 2 (REY. 12/83)
Date Channel #1 Startup Count Rate Level cpm Startup HV Hi-Level Cut-out amp (Ch 2)
Scram Checks Cnannel #2 High Level Setting amp
- Low Level Setting amp Period Trip Setting seconds Channel #3 High Level Setting (percent full " scale)
Low Level Setting (percent full scale)
Maximum High Level Trip
- amp Highest Operating Range full power scale I
Water Level Scram Water Temperature Scram 1
Replace Water Temperature Switch Earthquake Scram Manual Scram WATER CONDITION IN MAIN TANK CONTROL R00 LIMIT SETTINGS:
Lower Limit Upper Limit Fine Rod cm em Coarse Rod cm cm TIME TO INSERT RODS:
Cadmium in glory hole OK Safety Rod #1 40-50 see Safety Rod #2 40-50 sec Coarse Rod (High Speed) 40-50 sec Fine Rod (High Speed) 40-50 sec MANUAL SCRAM: OK l
II.A-1
_ _ . - ., .._,.y.. _ _. _ .. . . _ . , ___ ....,___,...-m__.,
MONTHLY REACTOR INSPECTION FORM, PAGE 2 0F 2 (REY.12/83)
. Date MAGNET CURRENT:
Magnet Current ma Low magnet current trip OK High magnet current trip level na NOTE: Scram level should not exceed 90 ma CHANNEL NO. 1 CHAMBER PLATEAU CHECK Vol tage CPM Amplifier CG Amplifier FG Discriminator Level Operating Yol tage a
EMERGENCY EVACUATION ALARM OK REMARKS:
I I
l l
Chief Reactor Supervisor l
l l IV.A-2 i
Section V Emergency Procedures Although the reactor has been designed to make operation as safe as possible, a set of emergency plans is necessary. Emer-gency, in this sense includes:
- 1) equipment or instrument failure or malfunction
- 2) abnormal behavior of the reactor
- 3) uncertainty of the operator as to the safety of con-tinued operation
- 4) failure of the operator to know the exact whereabouts of the Reactor Supervisor
- 5) fire
- 6) storm ..
- 7) riot
- 8) radioactive spill
- 9) power failure In the event of any emergency, the operator should immediately
- 1) Shut-down the reactor
- 2) Notify the Reactor Supervisor who in turn will notify the Chief Reactor Supervisor
- 3) Determine if there are excessive
- radiation levels 3a) If the emergency does not involve excessive radia-tion levels the operator should wait until the supervisor arrives, inform him of what happened, and adequately record any l
pertinent information in the log. The supervisor has the responsibility of determining the cause of the incident and tak-ing appropriate action.
3b) If there is any possibility that the emergency does involve excessive radiation levels the operator should:
- 4) Sound the Evacuation Alarm. The switch is located on the north wall of the Reactor Laboratory, near the exit.
- 5) Take a portable survey meter (or meters) and the log book with you if this does not cause a delay.
- Excessive radiation level is defined to be a dose rate at the console of >100 mrem /hr V-1
- 6) Leave by the nearest exit, making sure that all other personnel have evacuated the building.
- 7) Turn on the air circulation fans situated at the east door of the NE Laboratory Building.
- 8) Proceed to the " Hold Station" located in the open area immediately to the north of the Nuclear Engineering Laboratory Building.
- 9) Wait at the " Hold Station" for the Reactor Supervisor and Radiological Safety Officer. (It is the responsi-bility of the Reactor Supervisor to notify the Radiolog-ical Safety Officer immediately after being. notified.)
- 10) Do not attempt to leave the Hold Area or allow any one else to leave and do not attempt to re-enter the build-
. ing until authorization is given by the Chief Reactor Supervisor or Radiological Safety Officer.
- 11) If the emergency is caused by fire then the operator should notify the UNM police immediately before doing anything else (2242).
Note that according to our Emergency Plan, the Director of any emergency involving radiation is the Radiological Safety Officer or his deputy. The Director of any emergency not invol- ,
ving radiation is the Chief Reactor Supervisor.
l i
V-2
VI. Technical Soecifications APPENDIX A TO LICENSE NO. R-102 TECHNICAL SPECIFICATIONS FOR THE UNIVERSITY OF NEW MEXICO DATE July 1966 REVISED October 1969 1.0 Reactor Core 1.1 The excess reactivity with no experiments in the reac-ter and the control and safety rods fully inserted shall not exceed 0.002S delta k/k.
1.2 The reactor shall not be operated unless the core tank is sealed.
2.0 Control and Instrumentation Systems 2.1 The fine control rod, the coarse control rod, and the two safety rods shall be operable and the carriage posi. tion of the control rods shall be displayed at the console when-ever any rod is above its lower limit.
2.2 The worths of the control and safety rods shall pre-clude criticality by the insertion of a single rod and ensure subcriticality on the withdrawal of the coarse con- .
trol or any one safety rod.
2.3 During reactor operation, safety channels 2 and 3 shall be operating and shall sound an alarm and cause automatic reactor shutdown if the operating limit is reached.
2.4 A manual scram shall be provided on the reactor console and the safety circuitry shall be designed so that no single failure can negate both the autenatic and manual scram cap-abili ty.
VI-l J
2.5 The water in t'he shield water tank shall be no more ,
than 7 inches from the top of the shield water tank during reactor operation.
3.0 Experimental Limitations 3.1 The reactivity worth of experiments loaded into the reactor shall be limited so that the sum of all experiments with positive reactivity contributions shall not exceed 0.4 percent delta k/k.
3.2 All samples or experiments shall be doubly encapsulated .
and ensured leak tight if release of the contained material.s could cause corrosive attack to the facility, excessive con-tamination or chemical reactions that could possibly affect reactor safety.
3.3' No experiments shall be introduced into the core tank and no explosives or capsules containing materials which might combine. violently shall be irradiated in the reactor. .
4.0 Surveillance Recuirements 4.1 The safety system equipment listed in Table I shall be checked for calib-ation and proper condition at least semi-annually.
4.2 The excess reactivity and control rod worths shall be measured at least annually.
4.3 The coarse control rod and the two safety rods shall be removed from the reactor and checked for proper operation at least annually.
4.4 The requirements of this section are waived if the reactor has not been brought critical during the specified test intervals. However, the requirements must be fulfilled prior to subsequent startup of the reactor. -
VI-2
5.0 Administrative Recuirements
~
5.1 Organization a) An operating organization shall be established which shall review, approve, and promulgate all proce-dures and practices governing facility operations and facility modifications. This organization shall also provide for continuing review of operations, equipment performance, records and procedures.
b) A reactor safety committee shall be established which shall review and approve all proposed modifica-tions affecting reactor safety, and generai and specif-ic types of experiments. This committee shall conduct periodic audits of operations, equipment performance, records and procedures. The committee shall contain at least two members who are not in the operating organi-zation.
c) A radiological safety officer shall be appointed to review and approve all procedures and experiments on radiological safety. He shall enforce rules, regula-tions and procedures relating to radiological safety, and conduct routine radiation surveys. He may be a member of the operating organization provided that his duties do not also include the overall responsibility for facility operations.
5.2 Procedures a) Detailed written and acoroved procedures shall be -
provided for operation of the reactor and supporting facilities, maintenance operations, radiation protec-tion experiments, and emergency operations.
VI-3
b) Temocrary procedures which do not change the intent of the initial approved procedures may be authorized on approval by two members of the operating organization.
Such procedures shall be subsequently reviewed by the
- reactor safety connittee. i 5.3 Records - The reactor records shall contain routine l data regarding reactor operation including routine component j replacement and calibration, the action of operators and j experimenters, descriptions of all facility modifications, and details of any abnormalities and the corrective actions taken. .
1 p
l l
l VI-4 L
TABLE I Nuclear Instrumentation Channel No. Function Operating Limit 1 Monitor None 2 Low Power Scram 1 x 10-13 amperes High Power Scram 200% of licensed power Short Reactor Period 5-second minimum period l
3 Low Power Scram 5% of operating range High Power Scram 95% of operating range 200% of licensed power 6
l VI-5
APPENDIX B PHYSICAL SECURITY PLAN l
9 9
l 7
l 1
\
- ~ . . - - . - _. -- - . - - - .
l 4
APPENDIX C i
RADIOIDGICAL SAFETY i GENERAL EMERGENCY PLAN OF OPERATION j
j I. Purpose A. -The primary purpose of this plan is to minimize the
.I threat of physical violence to University personnel and property in times of campus. crisis and to expedite the return to normalcy following a state of emergency.
B. To support the overall University emergency plan by making available Radiological Safety personnel for consultation and surveillance during an emergency when radiations may be involved.
II. Conditions of Readiness A. Alert i 1. When a crisis situation is developing, the President will declare an " Alert".
- 2. Key personnel will assume their posts in the Control Center. .
B. Emergency
- 1. The President will declare an " Emergency".
- 2. Vice Presidents will disseminate information to personnel under their jurisdiction.
1
- 3. Emergency during working hours. Radiological Safety will secure windows, files and offices, and all but key personnel assigned specific duties will leave the University.
a 30 - . - _ -
A m ede 4A 4 6, 2AAf =.tiin5MW4J- _ a Ja Ad-&J4 Jim > A w da h m JA && M4-,4-eh@,iM..J144 4a,sh- - -'Ja - -
we - m4 .- - h4 J.E a An h+ &&ihMh 4.A A__._daR u a . k ,J mu m .m. naw m hMag__A.4 Mas,3
.h,-
l 1
l 2
1 a
4 4
1 a
t 4
1 4
i.
4
[
1 1- 6 b
I i
k i
i f
n k.
.I I
't e
1'
+
e l
f f.
l
- 4 i
d C
{
4
{
}'
b 1
l r
i' i1 h
h I'
i .
I L
b i
, i j
L 4
h-~_.---__.. _. _ _ _ , . . - . - - . - ..__ . -- -
s
- 4. The Campus Police are to be notified should key personnel need to leave a vacated building.
- 5. Emergency outside of working hours. Key personnel shall be notified to perform assigned functions as described in the departmental plan.
III. Protection of Personnel and Property 1
A. Personnel j
- 1. Personnel are not to resist physically any confrontation or occupatien of facilities when violence is overt or threatened.
- 2. When an emergency'is declared, all other than key personnel will leave the campus immediately and return to'their homes.
Radiological Safety shall establish an emergency post at the R.S. Lab at the Med'. School Bldg. 3. There will be at least two R.S. personnel available.
Key personnel:
- a. W.L. Tabor, Radiological Safety Officer, phone'7-2753. Home phone 299-3537.
- b. R.B. Counsellor, Radiological Safety Tech.,
phone 7-2753. Home phone 892-8212.
- c. Other technicians on call by Radiological Safety key personnel, and as needed to maintain 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> coverage of the emergency station.
31
B. Property
- 1. File cabinets, supply cabinets, and office doors will be locked. If time permits, typewriters and other portable office machines will be locked in cabinets or closets.
- 2. Occupied areas (R.S. lab Med) will have drapes closed. Non-occupied areas will have drapes or shades open and lights turned on. All radioactive materials are to be secured in locked cabinets or rooms having no windows.
IV. Supplemental to Departmental Plan s
A. Purpose
- 1. To minimize the threat of radiations to persons and the environs should there be fire, flooding, or vandalism in University areas having radioactive materials.
2.. To be available for consultation monitoring, and control of radiation incidents arising from violence or fire during an Emergency. -
B. Procedures
- 1. Radiological Safety Emergency Station, Med-3, Rm, 136
- a. Radiological Safety will man an emergency station at the Med. School, phone 7-2753.
- b. At least two persons are available at the station during early stages of the Emer-gency. Other technicians will be on call.
32
- c. R.S. vehicle (s) will be loaded with ,
monitoring equipment and other supplies to assist in the control or assessment of radiation incidents.
- 2. Emergency Response
- a. University Police, the Control Center, and Radiological Safety will coordinate activities as necessary to fulfill the purpose.
- b. When it is suspected or evident that I
buildings containing radioactalve materials have been disrupted, or fire has started (See listing in section D.), Radiological Safety must be notified immediately.
- c. As conditions permit, Radiological Safety l will assist in determining the severity of radiation implications, monitor for radiation, keep the Campus Police apprised of findings and recommendations. Assist in l ,
check-out of fire fighters and equipment after a fire involving radioactive materials.
C. Public Information Office In the event of serious fire that causes or threatens to cause a radiological disaster, the Public Information Office will collect information concerning the happenings for official relenses to news media and the City and State Public Relations Offices. The UNM 33
Public Information Office will coordinate its activities with key University personnel, such as the President of the University and the Vice President for Research in the Main Control Center.
D. Areas having Radiological Implications during an Emergency
- 1. Main Campus
- a. Biology (Entire building)
- b. Chemistry (basement, 2nd floor, 3rd floor)
- c. Farris Engr. Center (ground floor, 2nd floor, and entire Nuclear Laboratory)
- d. Geology (1st floor east wing & 3rd floor)
- e. Physics underground laboratory
- 2. North Campus
- a. UNMH (in-patient radioisotope areas) and nuclear Medicine
- b. Cancer Research Center (all floors)
- c. Medical School buildings Biological Medical Research .
Facility (all floors)
Med 1 (all floors) -
Med 2 Med 3 (Radiological Safety Laboratories) -
Med 5 Med 6
- d. Physics (main floor) 34
ucara Aso cturama
'"" Firc Sectice No. 3 Phnco .
,e l
ces
. O tjll,[,t,'
1.1,p; "T
IM) }. } - 766-4977 p' ~~~~
PublicInfar=atica!,dffida
-- -~ E j [, Ca: spun ?clico ?heca
_.C h%-
'N 277-2241 277-q813 ll _
~ ~ ' - ' ~
c
'a Radiological Safety l i- " ^ *
! W.N Lab 277-5806 .i I t
N RSO 277-5909 I, 7e ,
.h ll ;d
,. , h Medical Assistance l d' l i n* I 3 CMC 265-4411 . li l l- '
- 9. g} d - ) rStudent aealth cer.. .A! N : c- '"
'l
'? 2T>n26 r 'N i- 9- !
l
'Q f.:.gmy l
.gt
. , ,. (. l
- ' ~ + "
- - ,C #g o.j i d " ,' 0l y
\.W
...z+.cm..,[g\.b@
u e%.
a c
.f
- se.a er. _<lt.}s s.
1,. i, ,.
r ..
.s
=
i
- ~s
' 34 s
. . f.
%[ ak' Q , L .3 -). q w g. '
, y / MD [ , I, a W [a!; -
'.2.
n9 : ' ::::::s M y#. .-
cn.
- c=a 5 M p e-1 ii. . ;
'c
/
F;.-Q$s...
'A.*
- Ld
. , aMw..-
%pgM 9-nldj'gl=~ -Q:P3r :::
- . "%r m .
N M f;. 3 y,,
[r. s. %' . .&%N$S&!
- 'r'c. ' c
- :: y .3,.g# a.4 .--
w -
%.-dP
- t
% ,Y..9 W g- ,a.. g T i.
-A h.-t::y gi.- m t-Q L.s e J\
~-
, s *3 -g . -
E
g . 9 ,--b.5.C !.Y. - 3'" MJ-6 D
T r.- .- ii~
M e
h i h['
p=. $n'.
% l'M=kyMd'"%.Qg- Q';;;:$D'//C
, E P *b 6. 9 ~
- ===== f &.'.J%
M///g: Aw W..-.-= - -
wcs i, . 3 ./
g ' .
J xJ !gFY g g 1
- I i
'= G i ., .
-.E ..
f,.*** .l j
55= .!/a/Mdr'-)e%3nd5'1!3M'3hyr! T' : k. I$
W-
't C. .
kf
.g =;
- '='
- ' ~~ : ;f k'$- Y.Y,,,
Olt1 h*,h '? yC2sn...M : oG-Nk0; . t5 0' \
j,/ (, DdQ.'(*' ~ s j. M .- .'._#~'"'
" id-:.g L,,)
n --
rNm i
, wA -.
_, . i l i
.(
1
? y=-.+
, %g(g pf//. : :
!(l
-._.,=
gg
~
,G 3' jyyagM' oj. [0 .--J . .0 2' ' h . < g , r .--
, {.
Nc[6;'[.~;
'e~- %g = l]%.!.& _^
ip=:s.&
- , ,f$cean m W . g ,,,
.,ag,, . - )
- ue! T
+
. j -Qwn . --
--- Q ~
i Q., "
-R -
,. c;
---.--.. ~~~~.C :Ql,f 'w ? = . k _
_ -w -
y*.::s .. s , . _ _ -. :s _. x '
's &t&* 's 1 -
- I
,,, .f
~$ y
$J .t ug w 1 '. F' ' ' ' - - - - - ' ' ' ' '
) .!
l'=~. .; i' I i l .'=~ e N:%wU -i i
..... =*
THE UNIVERSITY OF NEW MEXICO ,,. -.. .-
CENTRAL AND NORTH CAMPUS PARKING -
- D CDU.S. f.'Alb,
THE UNIVERSITY OF NEW MEXICO Albuquerque, New Mexico EMERGENCY PLAN FOR RADIOLOGICAL SAFETY Wilbur L. Tabor, Director In conjunction with the overall emergency and disaster plan for the University of New Mexico, the Radiological Safety Officer and personnel
- are available for consultation and surveillance services.
Radiological Safety Office -- Office 277-27S3 Lab 277-2753 Home 299-3537 Accidents, or suspected accidents, involving radioactive materials or excessive ionizing radiation exposures to personnel shall be reported to the Radiological Safety Officer as soon as ,
possible. The Radiological Safety Officer shall determine if l
- Raymond Counsellor - Home phone 892-8212
- Louie Baca - Home phone 256-1142
- Pat Moore - Home phone 877-0715 36 . .
subsequent reporting is necessary to meet the requirements specified in Title 10, Part 10, of the Code of Federal Regulations, and as required by the State Board of Health.
The Radiological Safety Officer will act to minimize hazards by coordinating with one or more of the following agencies:
- 1. UNM Police--277-2241, coordinate activities with health services, state and city police and Albuquerque Fire and Rescue.
- 3. State of New Mexico Health Dept., Radiation Health, Santa Fe, New Me'xico, 984-002.0.
- 4. President of the University (to implement the
" Alert" or " Emergency" Plan)
Office--277-2626 Home --898-9250.
- 5. Sandia Base Emergency Monito'.ing Teams - ALO Duty Officer, 844-6952.
37
l I
APPENDIX c c
i E ICAL SPECIFICATIONS i
I t
r l
l 1
I I
i
{
r l
4 en
LICENSE NO. R-102 TECHNICAL SPECIFICATIONS FOR UNIVERSITY OF NEW MEXICO AGN-201M REACTOR (SERIAL #112)
DOCKET NO. 50-252 DATE: MAY 20, 1986 AS MODIFIED TO INCLUDE ANSI /ANS 15.1-1982 GUIDANCE 2
-- - .- . . = - _ -
TABLE OF CONTENTS PAGE 1.0 DEFINITIONS 8 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 11 2.1 Safety limits 11 2.2 Limiting Safety System Settings 11 3.0 LIMITING CONDITIONS FOR OPERATION 12 3.1 Reactivity Limits 12 3.2 Control and Safety Systems 13 ~
f 3.3 Limitation on Experiments 16 3.4 Radiation Monitoring, Controi, and Shielding 16 ,
4.0 SURVEILLANCE REQUIREMENTS 18 4.1 Reactivity Limits 18 4.2 Control and Safety Systems 19 4.3 Reactor Structure 20
, 4.4 Radiatich Monitoring and Control 20 l
l 5.0 DESIGN FEATURES 21 5.1 Reactor 21
- 5. 2' Fuel Storage 22 5.3 Reactor Room, Reactor Control Room, Accelerator Room 22 l
n )
e 3
TABLE OF CONTENTS (CONT)
PAGE 6.0 ADMINISTRATIVE CONTROLS 22 6.1 Organization 22 6.2 Staff Qualifications 26 6.3 Training 27 6.4 Reactor Safeguards Advisory Committee 27 6.5 Approvals 28 6.6 Procedures 28 6.7 Experiments 29 6.8 Safety Limit Violations 29 6.9 Reporting Requirements 29 6.10 Record Retention 33 e
l 1.0 DEFINITIONS The terms Safety Limit (SL) , Limiting Safety System Setting (LSSS),
and Limiting Conditions for Operation (LCO) are as defined in 50.36 of 10 CFR part 50.
1.1 Channel Calibration - A channel calibration is'an adjustment of the channel such that its output responds, within acceptable range and accuracy, to known values of the paramater which the channel measures. Calibration shall encompass the entire channel, including equipment, actuation, alarm, or trip.
1.2 Channel Check - A channel check is a qualitative verification of acceptable performance by observation of channel behavior. This verification may include comparison of the channel with other independent channels or methods measuring the same variable.
1.3 Channel Test - A channel test is the introduction of a signal into the channel to verify that it is operable.
1.4 ExDeriment - An experiment is any of the following:
- a. An activity utilizing the reactor system or its components or the neutrons or radiation generated therein;
- b. An evaluation or test of a reactor system operational, surveillance, or maintenance technique;
- c. The material content of any of the foregoing, including structural components, encapsulation or confining boundaries, and contained fluids or solids.
1.5 ExDerimental Facilities - Experimental facilities are those portions of the reactor assembly that are used for the introduction of experiments into or adjacent to the reactor core region or allow beams of radiation to exist from the reactor shielding.
Experimental facilities shall include the thermal column, glory hole, and access ports.
1.6 ExDlosive Material - Explosive material is any solid or liquid which
. . is categorized as a Severe, Dangerous or Very Dangerous Explosion Hazard in " Dangerous Properties of Industrial Materials" by N.I.
Sax, third Ed. (1968), or is given an Identification of Reactivity (Stability) index of 2, 3, or 4 by the National Fire Protection Association in its publication 704-M, 1966, " Identification System for Fire Hazards of Materials," also enumerated in the " Handbook for Laboratory Safety" 2nd Ed. ,(1971) published by The Chemical Rubber Co.
1.7 Measurina Channel - A measuring channel is the co'mbination of sensor, lines, amplifiers, and output devices which are connected for the purpose of measuring or responding to the value of a process variable.
t
l 1.8 Movable Experiment - A movable experiment is one which may be inserted, removed, or manipulated while the reactor is critical. l 1.9 Operable - Operable means a component or system is capable of performing its intended function in its normal manner. 1 1
, 1.10 coeratina - Operating means a component or system is performing its intended function in its normal manner.
1.11 Potential Reactivity Worth - The potential reactivity worth of an experiment is the maximum absolute value of the reactivity change that would occur as a result of intended or anticipated changes or credible malfuncticns that alter experiment position or configuration.
1.12 Reactor Comoonent - A reactor component is any apparatus, device, or material that is a normal part of the reactor assembly.
1.13 Reactor Ooeration - Reactor operation is any condition wherein the reactor is not shutdown.
1.14 Reactor Safety Svstem - The reactor safety system is that combination of safety channels and associated circuitry which forms an automatic protective system for the. reactor or provides information shich requires manual protective action be initiated.
1.15 Reactor Shutdown - The reactor shall be considered shutdown whenever
- a. either: 1. All safety and control rods are fully with-drawn from the core, or
- 2. The core fuse melts resulting in separation of the core, and
- b. The reactor console key switch is in the "off" position and the key is removed from the console and under the control of a licensed operator.
1.16 Removable Experiment - A removable experiment is any experiment, experimental facility, or component of an experiment, other than a permanently attached appurtenance to the reactor system, which can reasonably be anticipated to be moved one or more times during the life of the reactor.
1.17 Safety Channel - A safety channel is a measuring channel in the reactor safety system.
6_. _
1.18 Secured Ecuinment - Any experiment, or component of an experiment is deemed to be secured, or in a secured position, if it is held in a stationary position relative to the reactor by mechanical means.
The restraint shall exert sufficient force on the experiment to overcome the expected effects of hydraulic, pneumatic, bouyant, or other forces which are normal to the operating environment of the experiment or which might arise as a result of credible malfunctions.
l 1.19 Static Reactivity Worth - The static reactivity worth of an experiment is the value of the reactivity change which is measureable by calibrated control or regulating rod comparison methods between two defined terminal positions or configurations of the experiment. For removable experiments, the terminal postions are fully removed from the reactor and fully inserted or installed in the normal functioning or intended position.
1.20 Unsecured Exceriment - Any experiment, or component of an experiment e
is de'med to be unsecured whenever it is not secured as defined in 1.18 above. Moving parts of experiments are deemed to be unsecured when they are in motion.
t l
l l
I l
l 9
O
! 7
2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 Safety Limits Aeolicability This specification applies to the maximum steady state power level and maximum core temperature during steady state or transient operation.
Obiectiva To assure that the integrity of the fuel material is maintained and all fission products are retained in the core matrix.
Soecification
- a. The reactor power level shall not exceed 100 watts.
- b. The maximum core temperature shall not exceed 200 C during either steady state or transient operation.
Bases The polyethylene core material does not melt below 200 C and is expected to maintain its integrity and retgin essentially all of the fission products at temperatures below 200 C. The Hazards Summary Report dated February 1962 submitted on Docket F-15 by Aerojet-General Nucleonics calculated a steady state core average temperature rise of 0.44(AGN)gC / watt. Therefore, a steady state power level of Igo watts would result in an average core temperature rise of 44 C. Theg corresponding maximum core temperature would be below 200 C thus assuring integrity of the core and retention of fission products.
2.2 Limitina Safety System Settinas Aeolicability This specification applies to the parts of the reactor safety system which will limit maximum power and core temperature.
Obiective ;
To assure that automatic protective action is initiated to prevent a !
safety limit from being exceeded. )
Soecification
- a. The safety channels shall initiate a reactor scram at the following limiting safety system settings:
M
I 1
[
i Channel Condition LSSS l Nuclear Safety #2 High Power i 10 watts i Nuclear Safety #3 High Power $ 10 watts
- b. The polystyrene core thgrmal fuse melts when heated to a temperature of 120 C or less resulting in core I separation and a reactivity loss greater than 5%A k.
l Bases Based on instrumentation response times and scram tests, the AGN Hazards Report concluded that reactor periods in excess of 30-50 milli-seconds would be adequately arrested by the scram system.
l Since the maximum available excess reactivity in the reactor is less than one dollar the reactor cannot become prompt critical and the corresponding shortest possible period is greater than 200 milli-seconds. The high power LSSS of 10 watts in conjunction with automatic safety systems, and/or manual scram capabilities will assure that the safety limits will not be exceeded during steady state or as a result of the most severe credible transient.
In the event of failure of the reactor to scram, the self-limiting characteristics due to the high negative temperature coefficiegt,
- and the melting of the thermal fuse at a temperature below 120 C l wilg assure safe shutdown without exceeding a core temperature of 200 C 3.0 LIMITING CONDITIONS FOR OPERATION l 3.1 Reactivity Limits Aeolicability l
l This specification applies to the reactivity condition of the reactor and the reactivity worths of control rods and experiments.
Obiective To assure that the reactor can be shut down at all times and that the safety limits will not be exceeded.
l l Specification
- a. The available excess reactivity with all control and safety rods fully inserted and including the potential reactivity worth of all experiments shall not exceed 0.65% A k/k.
- b. The shutdown margin with the most reactive safety or control rod fully inserted shall be at least 1% Ak/k.
- c. The reactivity worth of the control and safety rods shall ensure subcriticality on the withdrawal of the coarse control rod or any one safety rod.
l 9
- d. The excess reactivity with no experiments in the reactor and and the control and safety rods fully inserted shall not exceed 0.25% A k/k.
Bases -
The limitations on total core excess reactivity assure reactor periods of sufficient length so that the reactor protection system and/or operator action will be able to shut the reactor down without exceeding any safety limits. The shutdown margin and control and safety rod reactivity limitations assure that the reactor can be brought and maintained subcritical if the highest reactivity rod fails to scram and remains in its most reactive position.
3.2 Control and Safety Systems ADolicability ,
These specifications apply to the reactor control and safety systems.
Obiective To specify lowest acceptable level of performance, instrument set points, and the minimum number of operable components for the reactor control and safety systems.
SDecification
- a. The total scram withdrawal time of the safety rods and coarse control rod shall be less than 1 second.
- b. The average reactivity addition rate for each control or safety rod shall not exceed 0.065% ak/k per second.
- c. The safety rods and coarse' control rod shell be interlocked such that:
- 1. Reactor startup cannot commence unless both safety rods and coarse control rod are fully withdrawn from the core.
- 2. Only one safety rod can be inserted at a time.
- 3. The coarse control rod cannot be inserted unless both safety rods are fully inserted.
- d. Nuclear safety channel instrumentation shall be operable in accordance with Table 3.1 whenever the reactor control or safety rods are not in their fully withdrawn position.
- e. The shield water level interlock shall be set to prevent reactor startup and scram the reactor if the shield water level falls 7 inches below the highest point on the reactor shield tank manhole opening.
10
- f. The shield water temperature interl,ock shall be set to prevent reactor startup and scram ghe reactor if the shield water temperature falls below 18
- g. The seismic displacement interlock shall be installed in such a manner to prevent reactor startup and scram the reactor during a seismic displacement.
- h. A loss of electric power shall cause the reactor to scram.
Bases 1
The specifications on scram withdrawal time in conjunction with the safety system instrumentation and set points assure safe reactor shutdown during the most severe foreseeable transients. Interlocks on control and safety rods assure an orderly approach to criticality a and an adequate shutdown capability. The limitations on reactivity addition rates allow only relatively slow increases of reactivity so that ample time will be available for manual or automatic scram during any operating conditions.
The neutron detector channels (nuclear safety channels 1 through 3) assure that reactor power levels are adequately monitored during reactor startup and operation. Requirements on minimum neutron levels will prevent reactor startup unless channels are operable and responding, and will cause a scram in the event of instrumentation failure. The power level scrams initiate redundant automatic protective action at power level scrams low enough to assure safe
, shutdown without exceeding any safety limits. The period scram conservatively limits the rate of rise of reactor power to periods which are manually controllable and will automatically scram the i reactor in the event of unexpected large reactivity additions.
The AGN-201's negative temperature coefficient of reactivity causes a reactivity increase with decreasing core temperature. The shield water temperature intgrlock will prevent reactor operation at temperatures below 18 C thereby limiting potential reactivity ,
additions associated with temperature decreases.
Water in the shield tank is an important component of the reactor shield and operation without the water may produce excessive radiation levels. The shield tank water level ihte'rlock will prevent reactor operation without adequate water levels in the chield tank.
The reactor is designed to withstand 0.6g accelerations and 6 cm j displacements. A seismic instrument causes a reactor scram whenever the instrument receives a horizontal acceleration that causes a horizontal displacement of 1/16 inch or greater. The seismic displacement interlock assures that the reactor will be scrammed and brought to a subcritical configuration during any seismic disturbance that may cause damage to the reactor or its components.
I 1
4 11
Table 3.1 Nuclear Instrumentation Channel No. Function ODeratina Limit 1 Monitor None
-13 2 Low Power Scram 1 x 10 amperes High Power Scram 200% of licensed power Short Reactor Period 5-second minimum period 3 Low Power Scram 5% of operating range High Power Scram 200% of licensed power O
12
The manual scram allows the operator to manually shutdown the reactor if an unsafe or othewise abnormal condition occurs that does not otherwise scram the reactor. A loss of electrical power de-energizes the safety and coarse control rod holding magnets causing a reactor scram thus assuring safe and immediate shutdown in case of a power outage.
, 3.3 Limitations on Eroeriments Anolicability This specification applies to experiments installed in the reactor and its experimental facilities.
Obiective To prevent damage to the reactor or excessive release of radioactive materials in the event of an experimental failure.
Soecification
- a. Experiments containing materials corrosive to reactor components or which contain liquid or gaseous, fissionable materials shall be doubly encapsulated.
- b. Explosive materials or materials which might combine violently shall not be inserted into experimental facilities of the reactor or irradiated in the reactor.
- c. The radioactive material content, including fission products of any doubly encapsulated experiment shall be limited so that the complete release of all gaseous, particulate, or volatile components of the experiment shall not result in exposures in excess of 0.5 rem whole body or 1.5 rem thyroid to persons occupying an unrestricted area continuously for a period of two hours starting at the time of release or exposure in excess of 5 rem whole body of 30 rem thyroid to persons occupying a -
restricted area during the length of time required to evacuate the restricted area.
Bases ,
These specifications are intended to reduce the likelihood of damage to reacto'r components and/or radioactivity releases resulting from an experimental failure and to protect operating personnel and the public from excessive radiation doses in the event of an experimental failure.
3.4 RADIATION MONITORING. CONTROL AND SHIELDING Acolicability This specification applies to radiation monitoring, control, and 13
reactor shielding required during reactor operation.
Obiective The objective is to protect facility personnel and the public from radiation exposure.
seecification
- a. An cperable portable radiation survey intrument capable of
- detecting gamma radiation shall be immediately available to reactor operating personnel whenever the reactor is not shutdown.
- b. The reactor room shall be considered a restricted area whenever the reactor is not shutdown.
- c. The reactor room shall be considered a radiation area whenever the reactor is operated.
- d. Whenever the reactor is operated at a power level equal to or greater than 0.9 watts the top of the reactor shall be considered a high radiation area and the access stairs to the top of the reactor shall be equipped with a control device which shall energize a conspicuous audible alarm signal in such manner that the individual using the stairs and the reactor operator are made aware of the entry,
- e. The following shielding requirements shall be fulfilled during reactor operation:
- 1. The reactor shield tank shall be filled with water to a height within 7 inches of the top of the shield water tank.
- 2. The thermal column shall be filled with water or graphite except during a critical experiment (core loading) or during other approved experiments requiring the thermal column to be empty.
- f. The core tank shall be sealed during reactor operation.
Bases 3 Radiation surveys performed under the supervision of a qualified health physicist have shown that the total gamma, thermal neutron, and fast neutron radiation dose rate in the reactor room, at the ,
closest approach to the reactor, is less than 50 mrem /hr at reactor power levels less than 5.0 watts (i.e., without access to reactor top).
The facility shielding in conjunction with radiation monitoring, control, and restricted areas is designed to limit radiation doses to facility personnel and to the public to a level below 10 CFR 20 l l
l i
limits under operating conditions, and to a level below criterion 19, Appendix A, 10 CFR 50 recommendations under accident conditions.
4.0 SURVEILLANCE REOUIREMENTS Actions specified in this section are not required to be performed if during the specifed surveillance period the reactor has not been brought critical or is maintained in a shutdown condition extending beyond the specified surveillance period. However, the surveillance.
requirements must be fulfilled prior to subsequent startup of the reactor.
4.1 Reactivity Limits Aeolicability This specification appies to the surveillance requirements for reactivity limits.
l Obiective To assure that reactivity limits for Specification 3.1 are not exceeded.
Soecification i
- a. Safety and control rod reactivity worths shall be measured annually, but at intervals not to exceed 16 months.
- b. Total excess reactivity and shutdown margin shsll be determined annually, but at intervals not to exceed 16 mor ths.
- c. The reactivity worth of an experiment shall be astimated or measured, as appropriate, before or during the first startup subsequent to the experiment's first insertion.
Bases The control and safety r.od reactivity worths are i.easured annually to assure that no degradation or unexpected charges have occurred which could adversely affect reactor shutdown margin or total excess reactivity. The shutdown margin and total exce ss reactivity are determined to assure that the reactor can always be safety shutdown with one rod not functioning and that the maximum possible reactivity insertion will not result in reactor periods shorter than those that can be adequately terminated by either operator or automatic action. Based on experience with AGN reactors, significant changes in reactivity or rod worth
- are not expected within a 16 month period.
15
4.2 Control and Safety Systems Aeolicability This specification applies to the surveillance requirements of the reactor control and safety systems.
Obiective To assure that the reactor control and safety systems are operable as required by Specification 3.2.
Soecification
- a. Safety and control rod scram times and average reactivity insertion rates shall be measured annually, but at intervals not to exceed 16 months.
- b. Safety and control rods and drives shall be inspected for proper operation annually, but at intervals not to exceed 16 months.
- c. A channel test of the following safety channels shall be
,~
performed prior to the first reactor startup of the day or prior to each reactor operation extending more than one day:
Nuclear Safety #2 and #3
- d. A channel test of the seismic displacement interlock shall be performed semiannually.
- e. A channel check of the following safety channels shall be performed daily whenever the reactor is in operation:
i Nuclear Safety #2 and #3
- f. Prior to each day's reactor operation or prior to each reactor operation extending more than one day, safety rod #1 shall be inserted and scrammed to verify operability of the
- manual scram system.
- g. The period, count rate, and power level measuring ch'annels shall be calibrated and set points verified annually, but at intervals not to exceed 16 months.
- h. The shield water level interlock and shield water temperature interlock shall be calibrated by perturbing the sending element to the appropriate set point. These calibrations shall be performed annually, but at intervals not to exceed 16 months.
RM.
Bases The channel tests and checks required daily or.before each startup will assure that the safety channels and scram functions are operable. Based on operating experience with reactors of this type, the annual scram measurements, channel calibrations, set point verifications, and inspections are of sufficient frequency to assure, with a high degree of confidence, that the safety system settings will be within acceptable drift tolerance for operation.
4.3 Reactor Structur.g, Aeolicability This specification applies to surveillance requirements for reactor components other than control and safety rods.
Obiective The objective is to assure integrity of the reactor structures.
Suecification Visual incoection for water leakage from the shield tank shall be
. performed annually. Leakage sufficient to leave a puddle on the floor shall be corrected prior to subsequent reactor operation.
Bases Based on experience with reactors of this type, the frequency of inspection and leak test requirements of the shield tank will assure capability for radiation protection during reactor operation.
4.4 Radiation Monitorinc and Control Anolicability This specification applies to the surveillance requirements of the -
radiation monitoring and control systems.
Obiective To assure that the radiation monitoring and control systems are operable and that all radiation and high radiation areas within the reactor facility are identified and controlled as required by Specification 3.4.
Specification
- a. All portable radiation survey instruments assigned to the reactor facility shall be calibrated under the supervision of the Radiological Safety Office annually, but at intervals not to exceed 16 months.
17
- b. Prior to each day's reactor operation or prior to each reactor operation extending more than one day, the reactor' access high radiation area alarm (Ref 3.4d) shall be verified to be operable.
- c. A radiation survey of the reactor room, shall be performed under the supervision of the Radiological Safety Office annually, but at intervals not to exceed 16 months, to determine the location of radiation and high radiation areas corresponding to reactor operating power levels.
Bases The periodic calibration of radiation monitoring equipment and the surveillance of the reactor access high radiation area alarm (Ref 3.4d) will assure that the radiation monitoring and control systems are operable during reactor operation.
The period radiation surveys will verify the location of radiation and high radiation areas and will assist reactor facility personnel in properly labeling and controlling each location in accordance with 10 CFR 20.
5.0 DESIGN FEATURES 5.1 Reactor
- a. The reactor core, including control and safety rods, contains approximately 667 grams of U-235 in the form of 20% enriched Uo, dispersed in approximately 11 kilograms of polyethylene.
The lower section of the core is supported by an aluminum rod hanging from a fuse link. The fuse melts at a fuse temperature of 120 C or less causing the lower core section to fall away from the' upper section reducing reactivity by at least 5% Ak/k.
Sufficient clearance between core and reflector is provided to insure free fall of the bottom hall of the core during the most severe transient.
- b. The core is 3 surrounded by a 20 cm thick high density
- (1.75 gm/cm ) graphite reflector followed by a 10 cm thick lead gamma shield. The core and part of the graphite reflector are sealed in a fluid-tight aluminum core tank designed to
, contain any fission gases that might leak from the core.
l
- j. c. The core, reflector and lead shielding are enclosed in and supported by a fluid-tight steel reactor tank. An upper or
" thermal column tank" may serve as a shield tank when filled with water or a thermal column when filled with graphite.
- d. The 6 1/2 foot diameter, fluid-tight shield tank is filled with water constituting a 55 cm thick fast neutron shield.
The fast neutron shield is formed by filling the tank with 18
approximately 1000 gallons of water. The complete reactor shield shall limit doses to personnel in unrestricted areas to levels less than permitted by 10 CFR 20 under operating conditions.
- e. Two safety rods and one control rod (identical in size) contain less than 15 grams of U-235 each in the same form as the core material. These rods are lifted into the core by electromagnets, driven by reversible DC motors through lead screw assemblies. De-energizing the magnets causes a spring-driven, gravity-assisted scram. The fourth rod or fine control rod.(approximately one-half the diameter of the other rods) is driven directly by a lead screw. This rod may contain fueled or unfueled polyethylene.
5.2 Fuel Storace Fuel, including fueled experiments and fuel devices not in the reactor, shall be stored in locked rooms in the nuclear engineering department laboratories. The storage array shall be such that K eff is no greater than 0.8 for all conditions of moderation and reflection.
5.3 Reactor Room. Reactor Control Room. Accelerator Room
- a. The reactor room houses the reactor assembly and accessories required for its operation and maintenance, and-the reactor control console.
- b. The reactor room is a separate room in the Nuclear Engineering Laboratory, constructed with adequate shielding and other radiation protective features to limit doses in restricted and unrestricted areas to levels no greater than permitted by 10 CFR 20, under normal operating conditions, and to a level below criterion 19, Appendix A, 10 CFR 50 recommendations under accident conditions.
- c. The access doors to the reactor room shall contain locks.
6.0 ADMINISTRATIVE CONTROLS 6.1 Orcanization .
The administrative organization for control of the reactor facility and its operation shall be as set forth in Figure 1 attached hereto.
The authorities and responsibilities set forth below are designed to comply with the intent and requirements for administrative controls of the reactor facility as set forth by the Nuclear Regulatory Commission.
l 19 1
i FIGURE 1 Administrative Organization of the Un!versity of New Mexico AGN-201M Reactor Facility NRC License R-102 4
President of the University Committee on Radiological Control Dean, College of Engineering i
Reactor Admini stra tor Radiological Reactor Safeguards Safety Officer Advisory Conmittee Chief Reactor m Superviser
- Reactor Operations Coc:nf ttee Reactor -
Supervisors I
"eactor Opera tors Reactor I Assistants Authorized Operators 4
a 20
6.1.1 President The President is the chief administrative officer responsible for the University and in whose name the application for licensing is l
made.
6.1.2 Dean. Collece of Encineerina The Dean of Engineering is the administrative officer responsible for the operation of the College of Engineering.
6.1.3 Reactor Administrator i Provides final policy decisions on all phases of reactor operation and regulations for the facility. He is advised on matters concerning personnel health and safety by the Radiological Control Officer and/or the Committee on Radiological Control. He is advised
! on matters concerning safe operation of the reactor by the Reactor Operations Committee and/or the Reactor Safeguards Advisory Committee. He designates Reactor Supervisors and names the Chief Reactor Supervisor. He approves all regulations, instructions and procedures governing facility operation. He submits the annual report to NRC. He issues and changes the code on the cipher locks of the Nuclear Engineering Laboratory Building at the beginning of each semester.
6.1.4 Radiolocical Safety Officer l
Normally represents the Committee on Radiological Control in matters concerning the radiological safety aspects of reactor operation. He is available for advice and assistance on radiological safety problems. He is the emergency director if an emergency involves radiation safety.
6.1.5 Reactor Safeauards Advisory Comnittee Reviews and evaluates reactor operations and procedures to ensure .
that the reactor shall be operated in a safe and competent manner.
At least two members of the RSAC are from organizations outside the University. The committee is available for advice and assistance on reactor operation problems. They must approve any major change in the facility. They normally meet twice a year (fall- and spring) .
They review the physical security plsn bi-annually.
6.1.6 Reactor Ocerations Committee Consists of the Reactor Supervisors with the Chief Reactor Supervisor. Other qualified persons may also be members. They are directly responsible to the Reactor Administrator for the preparation and submission of detailed procedures, regulations, forms, and rules to ensure the maintenance, safe operation, competent use and security of the facility. The Committee ensures that all the activities, experiments, and maintenance involving the
- 21
facility are properly logged and are,in accordance with established local and U.S. Nuclear Regulatory Commission regulations. They evaluate all proposed changes in procedure or changes in the i facility and must approve any minor change before the change is implemented.
6.1.7 Chief Reactor Suoervisor Holds a senior operator's license issued by the NRC. He is responsible for the distribution and enforcement of rules, regulations and procedures concerning operation of tho. facility. He has the authority to authorize any experiments or procedures which have receiverl appropriate prior approval by the Reactor Operations Committee, the Reactor Safeguards Advisory Committee and/or the Committee on Radiological Control (or the Radiological Safety
+
Officer) and have received prior authorization by the Reactor Administrator. He shall not authorize any proposed changes in the facility or in procedure until appropriate evaluation and approval has been made by the Reactor Operations Committee or che Reactor Safeguards Advisory Committee and authorization given by the Reactor Administrator. The Chief Reactor Supervisor is directly responsible for enforcing operating procedures and ensuring that the facility is
. operated in a safe, competent and authorized manner. He is directly responsible for all prescribed logs and records. He is the emergency director for emergencies not involving radiation.
6.1.8 Reactor Suoervisors Shall hold valid senior operator licenses issued by the Nuclear Regulatory Commission. A Reactor Supervisor shall be in charge of the facility at all times during reactor operation and must witness the startup and intentional shutdown procedures. The Reactor Supervisors are directly responsible to the Chief Reactor Supervisor. The Reactor Supervisors do not have to be present other than when the reactor is going critical or being shutdown. However, the location of the supervisor must be known to the Reactor Operator I
at all times during operation so that it is possible to contact '
him/her if required. -
6.1.9 Reactor Ocerators Must hold a valid operator's license issued by the NRC. They must conform to the rules, instructions and procedures for the startup, operation and shutdown of the reactor, including emergency procedures. Within the constraints of the administrative and supervisory controls outlined above, a reactor operator will be in direct charge of the control console at all times that the reactor is operating. The reactor operator is required to maintain complete and accurate records of all reactor operations in the operational logs.
l I
i 22
l 6.1.10 Authorized Ocerators ;
These are individuals who are authorized by the Reactor Supervisor 1 to operate the reactor controls and who do so with the knowledge of the Supervisor and under the direct supervision of a licensed
! Reactor Operator.
6.1.11 Reactor Assistant These are individuals who are present during a reactor operation to j provide assistance to the Operator as needed, with the exception l that a Reactor Assistant does not operate the controls of the reactor. In an emergency they may push the Reactor Scram button.
6.1.12 Oceratina Staff
- a. The minimum operating staff during any time in which the reactor is not shutdown shall consist of all of the following:
One licensed Reactor Operator in the reactor control room.
One other person in the reactor room or reactor control room qualified to activate manual scram and initiate
! emergency procedures.
One licensed Senior Reactor Operator readily available on call. This requirement can be satisfied by having a licensed. Senior Reactor Operator perform the duties stated 1 in paragraph 1 or 2 above or by designating a licensed Senior Reactor Operator who can be readily contacted by telephone and who can arrive at the reactor facility within 30 minutes.
- b. A licensed Senior Reactor Operator shall supervise all reactor maintenance or modification which could affect the I reactivity or the reactor.
l l
6.2 Staff Oualifications The Chief Reactor Supervisor, licensed Reactor Operators, and i technicians performing reactor maintenance shall meet the minimum __
qualifications set forth in ANS 15.4, " Standards for Selection and Training of Personnel for Research Reactors". Reactor Safeguards Advisory Committee members shall have a minimum of five (5) years
- experience in their profession or a baccalaureate degree and two (2) years of professional experience. The Radiological Safety Officer shall have a baccalaureate degree in biological or physical science and have.at least two (2) years experience in health physics.
6.3 Trainina The Head of the Department of Nuclear Engineering shall be i responsible for directing training as set forth in ANS 13.4, l
4 23
" Standards for Selection and Training of Personnel for Research Reactors". All licensed reactor operators shall participate.in requalification training as set forth in 10 CFR 55.
6.4 Reactor Safeauards Advisory Committee 6.4.1 Meetinas and Ouorum The Reactor Safeguards Advisory committee shall meet as often as l deemed necessary by the Reactor Safeguards Advisory Committee chairman but shall meet at least once each calendar year. A quorum for the conduct of official business shall be three (3) members.
6.4.2 Reviews l The Reactor Safeguards Advisory Committee shall review:
- a. Safety evaluations for changes to procedures, equipment or systems, and tests or experiments, conducted without Nuclear Regulatory Commission approval under the provision of 10 CFR 50 paragraph 50.59 to verify that such actions do not constitute an unreviewed safety question.
- b. Proposed changes to procedures, equipment or systems that
, change the original intent or use, and are non-conservative, or l those that involve an unreviewed safety question as defined in 10 CFR 50 paragraph 50.59.
- c. Proposed tests or experiments which are significantly different from previous approved tests or experiments, or those that involve an unreviewed safety question as defined in 10 CFR 50 paragraph 50.59.
- d. Proposed changes in Technical Specifications or licenses.
- e. Violations of applicable statutes, codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
- f. Significant operating abnormalities or deviations from normal and expected performance of facility equipment that affect nuclear, safety.
- g. Reportable occurrences.
- h. Audit reports.
6.4.3 Audits Audits of facility activities shall be performed at least annually under the cognizance of the Reactor Safeguards Advisory Committee -
but in no case by the personnel responsible for the item audited.
These audits shall examine the operating records and encompass but shall not be limited to tne following:
- a. The conformance of the facility operation to the Technical Specifications and applicable license conditions, at least annually.
- b. The Facility Emergency Plan and implementing procedures, at least every two years.
- c. The Facility Security Plan and implementing procedures, at least every two years.
6.4.4 Authority The Reactor Safeguards Advisory Committee shall report to the Reactor Administrator and shall advise the Chief Reactor Supervisor on those areas of responsibility outlined in Section 6.1.5 of these Technical Specifications.
6.4.5 Minutes of the Reactor Safecuards Advisory Committee one member of the Reactor Safeguards Advisory Committee shall be designated to direct the preparation, maintenance, and distribution of minute.s of its activities. These minutes shall. include a summary of all meetings, actions taken, audits, and reviews.
6.5 Acorovals The procedure for obtaining approval ~for any change, modification, or procedure which requires approval of the Reactor Safeguards Advisory Committee shall be as follows:
- a. The Chief Reactor Supervisor shall prepare the proposal for review and approval by the Reactor Administrator.
- b. The Reactor Administrator shall submit the proposal to the Reactor Safeguards Advisory Committee for review and comment.
- c. The Reactor Safeguards Advisory Committee can approve the
- proposal'by majority vote.
6.6 Procedures There shall be written procedures that cover the following activities:
- a. Startup, operation, and shutdown of the reactor.
- b. Fuel movement and changes to the core and experiments that could affect reactivity.
- c. Conduct of irradiations and experiments that could affect the operation or safety of the reactor.
- d. Preventive or corrective maintenance which could affect the safety of the reactor.
25
- e. Surveillance, testing and calibration'of instruments, components, and systems as specified in Section 4.0 of these Technical Specifications.
- f. Implementation of the Security Plan and Emergency Plan.
I' The above listed procedures shall be approved by the Dean of the College of Engineering and the Reactor Safeguards Advisory i Committee. Temporary procedures which do not change the intent of previously approved procedures and which do not involve any unreviewed safety question may be employed on approval by the Chief Reactor Supervisor.
6.7 Exneriments
- a. Prior to initiating any new reactor experiment an experimental procedure shall be prepared by the Chief Reactor Supervisor and reviewed and approved by the Reactor Safeguards Advisory Committee.
- b. Approved experiments shall only be performed under the cognizance of the Chief Reactor Supervisor.
6.8 Safety Limit Violation The following actions shall be taken in the event a Safety Limit is violated:
- a. The reactor will be shut down immediately and reactor operation will not be resumed without authorization by the Nuclear Regulatory Commission (NRC).
- b. The Safety Limit Violation shall be reported to the appropriate NRC Regional Office of Inspection and Enforcement, the Director
, of the NRC, and the Reactor Safeguards Advisory Committee not later than the next work day.
- c. A Safety Limit Violation Report shall be prepared for review by the Reactor Safeguards Advisory Committee. This report shall describe the applicable circumstances precpding the violation, the effects of the violation upon facility components, systems, or structures, and corrective action to prevent recurrence.
- d. The Safety Limit Violation Report shall be submitted to the NRC, and the Reactor Safeguards Advisory Committee within 14 days of the violation.
6.9 ReDortina Recuirements In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the appropriate NRC Regional Office.
m
609.1 Annual Oceratina Report Routine annual operating reports shall be submitted no later than ninety (90) days following the end of the operating year. The annual operating reports made by licensees shall provide a comprehensive summary of the operating experience having safety significance that was gained during the year, even though some repetition of previously reported information may be involved.
References in the annual operating report to previously submitted reports shall be clear.
Each annual operating report shall include:
- 1. A brief narrative summary of
- a. Changes in facility design, performance characteristics, and operating procedures related to reactor safety that occurred during the reporting period.
- b. Results of major surveillance tests and inspections.
- 2. A tabulation showing the hours the reactor was operated and the energy produced by the reactor in watt-hours.
- 3. List of the unscheduled shutdowns, including the reasons therefore and corrective action taken, if any.
- 4. Discussion of the major safety related corrective maintenance performed during the period, including the effects, if any, on the safe operation of the reactor, and the reasons for the corrective maintenance required.
- 5. A brief description of:
- a. Each change to the facility to the extent that it changes a description of the facility in the application for license and amendments thereto. .
- b. Changes to the procedures as described in Facility Technical Specifications.
- c. Any new or untried experiments or tests performed during the reporting period.
- 6. A summary of the safety evaluation made for each change, test, or experiment not submitted for NRC approval pursuant to 10 CFR 50, paragraph 50.59 which clearly shows the reason leading to the conclusion that no unreviewed safety question existed and that no technical specification change was required.
27
- 7. A summary of the nature and amount of radioactive effluents released or discharged to the environs beyond the effective control of the licensee as determined at or prior to the point of such release or discharge.
- a. Licuid Waste (summarized for each release)
- 1. Total estimated quantity of radioactivity released (in Curies) and Total volume (in liters) of effluent water (including diluent) released. l I
- b. Solid Waste (summarized for each releasel l
- 1. Total amount of solid waste packaged (in cubic meters)
- 2. Total activity in solid waste (in Curies)
- 3. The dates of shipments and disposition (if shipped off site).
- 8. A description of the results of any environmental radiological surveys performed outside the facility.
- 9. Radiation Exposure - A summary of radiation exposures greater than 100 mrem (50 mrem for persons under 18 years of age) received during the reporting period by facility personnel or visitors.
6.9.2 Recortable Occurrences Reportable occurrences, including causes, probable consequences, corrective actions and measure to prevent recurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of the occurrence. In case of corrected or supplemental reports, an amended licensee event report shall be i completed and reference shall be made to the original report date.
l
- a. Promot Notification with Written Followuo The types of events listed below shall be reported as expeditiously as possible by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of the appropriate NRC Regional Office, or his designated' representative no later than the first work day following the event, with a written followup report within two weeks. Information provided shall contain narrative material to provide complete explanation of the circumstances surrounding the event.
28
- 1. Failure of the reactor protection syste'm or other systems subject to limiting safety system settings to initiate the required protective function by the time a monitored parameter reached the setpoint specified as the limiting safety system setting in the technical specifications or failure to complete the required protective function.
- 2. Operation of the reactor or affected systems when any parameter or operation subject to a limiting condition is less conservative than the limiting condition for operation established in the technical specifications without taking permitted remedial action.
- 3. Abnormal degradation discovered in a fission product barrier.
- 4. Reactivity balance anomalies involving:
- a. Disagreement between expected and actual critical rod positions of approximately 0.3% 4 k/k.
- b. Exceeding excess reactivity limit.
- c. Shutdown margin less conservative than specified in technical specifications.
- d. If sub-critical, an unplanned reactivity insertion of more than approximately 0.5% A k/k or any unplanned criticality.
- 5. Failure or malfunction of one (or more) component (s) l which prevents or could prevent, by itself, the l fulfillment of the functional requirements of system (s) used to cope with accidents analyzed in the Safety Analysis Report.
- 6. Personnel error or procedural inadequacy which prevents, could prevent, by itself, the fulfillment of the
- functional requirements of system (s) used to cope with accidents analyzed in the Safety Analysis Report.
- 7. Unscheduled conditions arising from natural or man-made events that, as a direct result of the event, require reactor shutdown, operation of safety systems, or other protective measures required by Technical Specifications.
- 8. Errors discovered in the transient or accident analyses or l
in the methods used for such analyses as described in the Safety Analysis Report or in the bases for the Technical Specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.
l 29 t
- 9. Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analysis in the Safety Analysis Report or Technical Specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.
6.9.3 Special Reoorts Special reports which may be required by the Nuclear Regulatory commission shall be submitted to the Director of the appropriate NRC Regional Office within the time period specified for each report.
6.10 Record Retention 6.10.1 Records to be Retained for a Period of at Least Five Years
- a. Operating logs or data which shall identify:
- 1. Completion of pre-startup checkout, startup, power changes, and shutdown of the reactor.
- 2. Installation or removal of fuel elements, control rods, or experiments that could affect core reactivity.
- 3. Installation or removal of jumpers, special tags or notices, or other temporary changes to reactor safety circuitry.
- 4. Rod worth measurements and other reactivity measurements.
- b. Principal maintenance operations.
- c. Reportable occurrences.
- d. Surveillance activities required by technical specifications.
- e. Facility radiation and contamination surveys.
- f. Experiments performed with the reactor.
This requirement may be satisfied by the normal operations log book plus,
- 1. Records of radioactive material transferred from the facility as required by license.
- 2. Records required by the Reactor Safeguards Advisory Committee for the performance of new or special experiments.
- g. Changes to operating procedures.
30
6.10.2 Records to be Retained for the Life of the Facility
- a. Records of liquid and solid radioactive effluents released to the environs.
- b. Appropriate off-site environmental monitoring surveys.
- c. Fuel inventories and fuel transfers.
- d. Radiation exposures for all personnel,
- e. Drawings of the facility.
- f. Records of transient or operational cycles for those components designed for a limited number of transients or cycles.
- g. Records of training and qualification for members of the facility staff.
- h. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
- i. Recceds of meetings of the Reactor Safeguards Advisory Board.
O
APPENDIX D SAFETY ANALYSIS REPORT o
9 e -
4 SAFETY ANALYSIS REPORT for the Univet.ity of New Mexico AGN-201M Reactor Facility Facility License No. R-102 The University of New Mexico Albuquerque, New Mexico 87131 May 1986 pr e
. ,m .J
1 TABLE OF CONTENTS PAGE I. Introduction 3 II. General Design Features 3 III. Reactor Location 20 A. Reactor Site 20 B. Meteorology 20 C. Geology & Hydrology 23 D. Seismology 26 E. Demography 29 IV. Reactor Building 29 A. Laboratory Building 19 B. Reactor Laboratory 29 V. Safety of Facility 32 A. Maximum Credible Accident 32 B. Shielding 32 VI. Reactor Safety Evalutaion 33 Appendices A. Maximum Credible Accident B. Recorded Earthquakes 1
I. Introduction ,
a The University of New Mexico AGN-201 Reactor (SN-112) was transferred from the Berkeley campus of the University of California and bGgan operation at the University of New Mexico in September of 1966. In tha early months of 1969 the reactor was moved to its present site in the Nuclear Engineering Laboratory and the operating power level was increased to 5 watts with the installation of new controls and instrumentation.
Since that time the reactor has been regularly used as an operations training reactor and for student laboratory experiments.
II. The AGN-201 Reactor System A. React 7r Description The AGN reactor is a homogeneous thermal reactor which is used for teaching and training. Figure 1 is a simple schematic of the reactor.
Figure 2 is a detailed section plan. Figure 3 shows the core tank and its contents.
The reactor core is 25.6 cm diameter x 24 cm high. It consists of nine fuel discs which are separated at the midplane by a thin aluminum baffle. A 1 in diameter glory hole passes through the center of the Core.
The fuel is 20 percent enriched UO stabilized polyethylene. The polyethylen$ power acts asembedded in radiation the moderator.
Full details of the fuel are given in Table 1. Total fuel loading including the fuel rods is 667 g of U-235.
There is a space at the top of the core for expansion and fission product gas accumulation.
The core fuse is a polystyrene plug which supports ghe bottom half of the core. If the temperature reaches approximately 100 C , the fuse will melt and the lower three fuel discs will fall ~4 in., shutting the reactor down. Fuse operation is as follows. There is a higher fuel loading (2 x fuel density) in the fuse so during operation more heat is generated in the fuse than in the core. The temperature in the fuse rises
, about twice as fast as the temperature in the core.
The core is contained in a gas-tight aluminum cylindrical tank (32.2 cm diameter x 76 cm high). The core bank can be considered to consist of an upper and lower section separated by an aluminum disc or baffle.
The reflector consists gf graphite on all sides of the core. It is 20 cm thick, density 1.75 g/cm . Part of the graphite is in the core tank and part outside. There are four, 10 cm diameter, access holes which pass through the graphite outside the core can.
3
TT N Water tank Water Reactor tank Core tark Lead g ,
Graphit mg Access ports
- Core I Ionization chamber (linear)
. Ionization .chambe Fission chamber (ch.1)
(log) (ch. 2)
M l l
Manhole cover G,1 ory hol e Figure 1. Schematic of the reactor (1 coking frcm above).
4
t 6.5 ft :
lianhole _
} I i
55 cm Water
-'- ~^-
Thermal Column Tenk Shield ---- k C r\] 7 \- - -
or Water Tank
~[ ,77777777777777 7 7, 7
10 cm Lead \ /f --- -- - Core Shield ^
~
~
2 h, s n
nN y'/ / ~~
r 25 cm x 25 cm Cylinder
- ~
/- b f Glory Hole - - -
/
/
/
7.K s 4\ f' 20 cm Graphite
~ ~. -- / } s\
1 in diam. - -
Reflector access ports . ~--/-/ f . - - -
. &b- x N
r a- -
--- g -
- 9.5 ft Base
_~ Controlled Access Arec T
Figure 2. AGN Model 201 M Reactor.
5
-.-... ~ .- _ .. ..... ,../ . .
'<',' I!,'I,$' '.,$'I,'/,tk
,' '/ , g Sn;,cy;;7,=._~_., _,3cy cg f'$,. * '/, ,///,,', /// / ,:x//,,'//'/N)
',//i,.
/,', -
s
$s,'//,'i
,/
, , , , i/ ,/ ./ ',, ,/l ,:,/y' '// i /<, / ' /, ,^z ,
%'/l/l.,,,'/'///f..:-> / / ~ui2
/ /D/SCS
, h .. . ,/ /,,.'/ .r' w' .mm.wumwww.w-c '.:ww.ws crusc .; g_cpy ya_,_g cgr,9w'NwT.** N "ssmL'EMW-f
$'@2%
iN' ,
l d'MAEKY/4A i (hb',
'64M l' l ) F '974."' , l;90'1
~s'WERMl r~LGE f,ff 7gt)'
- $k Y - CORE iA' NK
. .. )' d'N'** . .',, 'N,4
, M ., ,y
- ., ..y s '. . .y,;
7 , . , ' . ..
._ ' . N, '
N CONTROL LSAn i f u
~ l~., %' I 200 TH/M2!.ES I '\Q. :' .
L,.' '<j C.
. .n k.11 il,.Yl'$
l
~ $$$%c;.=. .su=cerAs.su.
f
/-
n . u.
1 g - e t s
, g y :u
. wy, g-- ~. -m,
- p. n ..
y b.
Y C n 1 CME 7A" NKCC'.En s
C t
2 4
3 3 :
- ; : d Figure 3. AGN-201M Core Tank and Contents.
6
l l
l 1
NUCLEAR ENGINEERING UNIVERSITY OF NEW MEXICO TABLE 1. AGN-201 FUEL LOADING Total Mass 0-235 Mass (gm) (gm)
Fuel Piece 2150.0 98.89 Disk 20497 Disk 20498 4 cm x 25.6 dia. 2158.5 99.12 2026.5 93.17 Disk 20499 Disk 204100 2052.0 94.39 1262.5 58.01 Disk 204101 2 cm x 25.6 cm dia. 1263.5 58.07 Disk 204102 1263.0 58.05 Disk 204103 1 cm x 25.6 cm dia. 670.0 30.80
[ Disk 204104 Disk 204105 743.5 29.76*
,5.86 0.41 Core Puse Fixed Fuel Subtotal - 620.67 Safety il 315.77 14.51 Safety #2 315.53 14.50 235 315.58 14.51
' Coarse Rod 0.627 cm U /cm Fine Rod 0.112 gm'U235/cm 58.95 2.71 Moveable Fuel Subtotal - 46.23
\
Total Loaded Fuel - 666.90 g Disc 20497 is the bottcm disc in the core, Disc 204105 is the top disc in the core as shown in Figure 4.
The approximate critical mass is 665 g U-235.
l The excess reactivity at 18'C with the glory hole empty is 0.25 percent, ox/K.
7
AGN-201 FUEL LOADING I
L None _____e ,Non 204105 ,
j 204104
_ _ _ _ _ J 204103 l 1-- - I 1 1 204102 204101 204100 A
V s
20499 20498 20497 Figure 4. AGN-201 Fuel Loading.
The graphite is surrounded by a 10 cm thick lead shiold. The chielding, reflector and core are enclosed and supported by a thick steel reactor tank (47.5 cm radius). The removable thermal column tank is provided to permit access to the core tank. This is normally filled with water to provide biological shielding. It can be filled with graphite if a thermal column is desired. The steel tank acts as secondary containment for the core tank and is fluid tight. No experiments are allowed in the core tank. The control and safety rods enter through the bottom of the reactor tank.
The water tank is the third and outermost of the fluid tight -
containers. It is 6 1/2 feet in diameter and made of steel. It holds
- 1000 gallons of water and forms the fast neutron shield.
Finally, there is a 60 cm concrete shield in front of the reactor tank--and 40 cm on the sides and back. There is no shielding on the top j of the reactor tank.
The four, 10 cm diameter access ports are loaded as follows:
l
< 40 cm> < 10 cm > < - 70 cm > ,
Wood Lead Graphite Lead Wood I I l The reactivi'ty worths are: Wood slug c 0.0027%
10 cm lead c 0.019%
20 cm graphite = 0.21%
! The access ports are labelled on the reactor:
3 1 1 3 N S Face Face 4 2 2 4 The 2 Ci Pu-Be source and source drive are mounted in access port
- 2 on the North Face. The source drive is shown in Figure 5.
The auxiliary ionization chamber is mounted in access port #4 on the South Face.
B. Standard Loadings The following standard loadings are defined. These loadings comply with the requirement that the excess reactivity with the standard loading does not exceed 0.25 percent with no experiments in the reactor and the control and safety rods fully inserted.
. Standard Loading #1: The glory hole is empty, all access port fillers are in their normal positions, and the fine control rod contains polyethylene rod sections.
9 .
82.5 ca .
?
Al Liner S Water "
(3 cm ID) j f Tank Wall 14.5 cm- = -
5 cm a 28 cm
!!!! l .\ \ '\
. \- Cadmium Wrapped Paraf fin ' / < . !/
. //
10 cc A h Source Can
,]tenna g, j 7h ///L ////!/.il J ; %\' O 6%9%W 8 _:_
h w p wnw -xww W d
/
Antenna 28 cm Wood f\
[ g; j .
Hountin,a/
g : Total Source Travel "IN" Dracket j "OUT" limit Switph Limit Switch Access Port 2 5
""U PuBe SOURCE DRIVE ASSEMBLY I= 17.1 cm 1 I -
13.3 cm le --
w ....... .... .... ...... .... ................-111 2 Ci PuBe
] Luctte Plug (fH-1040) 3 cm sim17thmn -
--- 5. 7 cm -
Aluminum Source can x2 x 106 n/sec Figure 5 Punn Source Can Detafl; PuBe Source Drive Assembly.
Standard Loading #2: The glory hole is empty, half of the access port fillers in port 4 are removed (C Pb, and wood) and a boron-lined ion chember is fully inserted into the remaining cavity. .The rest of the envity is then filled with paraffin or polyethylene and the access port is ccaled and locked. The fine control rod contains normal fuel material rod ccctions.
Standard Loading #2 (amended): This is the same as Standard Londing #2 except that the 2Ci Pu-Be source and source drive are mounted in the northside of access port 2.
C. Reactor Control The AGN-201 reactor has two safety rods, a coarse control rod and a fine control rod. Reactivity increases as these rods are inserted.
Two Safety Rods #1, #2: These are 5 cm in diameter, and contain 14.5 g of U-235 in polyethylene. The active length of the rod is 15 cm.
The active fuel is doubly encapsulated in two aluminum containers. This icolates the fuel in the rods from the core. The total travel is 24 cm.
The insertion time is 40 to 50 sec full length. The scram removal time is approximately 200 msec. The total reactivity is 1.25 percent A k/k per rod.
Coarse Rod: This is 5 cm in diameter and again travels 24 cm. The active length is 15 cm. It can be inserted at high or low speed. It contains 14.5 g U-235 in polyethylene, again doubly contained in aluminum. Normal insertion / withdrawal time (high) speed is 40 to 50 sccs. The slow speed insertion time is approximately twice the fast speed insertion time. Scram time is =200 msec. The reactivity worth is of the order of 1.25% ak/k.
The safety rods and the coarse rod are magnetically coupled to a carriage and they compress a spring in fully inserted position. Thus the rcmoval of the electromagnet current results in the withdrawal of the rod by gravity with an assist from the compressed spring.
The rod carriages are mechanically driven to full out position following a reactor scram.
Fine Rod: This is mechanically coupled to the carriage. It contains 2.71 g of U-235 in polyethylene, again doubly contained. It -
travels 24 cm and is 2.5 cm in diameter. It can be inserted at high or low speeds. Normal insertion / withdrawal time is 40 to 50 sec (high speed). The low speed insertion time is approximately twice the fast insertion time. The fine rod does not scram.
Total worth of the fine rod is -0.25 percent Ak/k.
Small adjustments of the excess reactivity of the reactor can be made by adjusting the control rod travel. This is done by altering the position of the top limit switches. This is done to ensure that the excess reactivity <0.25 percent with no experiments in the reactor at the u
minimum operating temperature. The rods are inserted in the sequence of Safety Rod 1; Safety Rod 2; Coarse and Fine Rods together or separately.
Figure 6 shows the control rod mechanism. A scram opens the holding magnets on the safety and coarse rods so that these fall under gravity, ass.isted by compressed springs, to a full-out safe position. A warning light and bell indicate that this has happened. A more detailed view of the rod drive mechanism is shown in Figure 7. The coarse rod reactivity calibration curve is shown in Figure 8. Figure 9 shows the partial fine rod calibration curve; Figure 8b shows the partial coarse rod
. calibration.
Rod In-Rod Out: The rod-in red light, rod-out green light and the rod-engaged yellow light are activated by micro-switches.
The safety systems are " fail safe". A scram signal or power failure will de-energize the holding magnet allowing the safety and coarse control rods to be accelerated downwards and out of the core by gravity and spring loading.
The sequence of SR1, SR2 is required by the drive circuitry. The coarse control rod cannot be driven in until both SRI and SR2 are fully inserted.
D. Instrumentation and Safety Systems
- 1. Nuclear Instrumentation
- a. Channel 1 - U-235 Fission Chamber This detector is a source-range detector of neutron flux used as a start-up monitor. The electronics consist of an ORTEC 109PC preamp, an ORTEC 485 amplifier, and an ORTEC Discriminator-Scaler. The signal is generated by a gas-filled U-235 fission chamber which is biased to approximately +250 V for operation as an ionization chamber. The high voltage on the chamber is automaticalgy switched off when the signal from Channel 2 exceeds 10 amps to prolong the life of the detector,
- b. Channel 2 - Boron-lined Ionization Chamber Proper operation of Channel 2 is a license requirement.
It provides both log picoammeter and period meter responses. The detector consists of a positively-biased
(~600 volts) boron-lined, gas-filled ionization chamber.
The log picoammeter and period meter are used to assure operation within power (less than 10 watts or 2 times licensed powgy; and period (T> 5) limits. A low current (I $ 2 x 10 amps) scram on this channel assures detector operation over the entire source to full power range of operation of the AGN.
7- gv r y- _
-n-,+_ya, . ,, y ,y,_q_.,..y _, --.,m. ._., , . _ , , , , , . , , _ , . _ _ ~ _ _ _ , , , , . , , , _ _ , , _ _ _ , , , , , ,
,r- .
l 1
~ ~
=:
4 -
g "ae CAPSULE
{
I '
I I
I \
l 1
1 jw 1!
j i
" l L.
I D
\b
'a i BEARING MAGNET g
if.
(* II hIlh LEAD SCREW I
y ,
Dy iel n_ -
_ )
'N g ri-l DASH POT 4
F p-l CHAIN DRIVE i MOTOR 1
- ww ~-_ 4
~Piyb ~g SYNCHROS S -
Figure 6. Control Rod.
13
/y Fuel Rod Scr:ws in at this Point
- Control Rod Guide Tube
. l II i1 5 l l q I 1
< - > . pgja g l
l_ ~_
4 h. J Upper Limit Switch d a Set Point t,
-- - l c- 2 l
==-
l .
Y t WI-
- l---~l i.
Drivan Lead Screw
- d. ' ] ; Stationary Lead Screw
<- r (Does not turn)
<- c- ,
.- '"-~~~ )
'---~~ ' - p
. 5 -
l l 1 l l l H
I l [II <%)
<- l 1l 1 I i1l
--- -f Upper Limit Switch
.,___ I .-
1 I
- ---- ,' II I IlI I ,
~
-Traveling Magnet
< ri / :d c ' Rod -
,___ )
'" l Engaged - -
'--~~ ' '~
w, 'Limi: .-
. Couplino. Lengtn
_ .=- . - - . Switch
> - d-d P
.w
. . c ._
Scram SpringJ
- l __ 3-Scram Spring d- a
. Not Shown l '~~' 5 j Two additional travelino a
f, i agnet guide rods b ' l '~"~~ synchro generator (chain K
Ed .
d driven by de motor)
. Lower limit switch (rod out switch) i i i ' ' -
ie Ie ii ll ; i i o d O il Chain Driver Dash-Gear pot dc Motor Figure 7. Rod Drive Mechanism.
14
1:0-
. 161 -
, 140 -
120 -
m y Feb. 9, 1982
~
8
>, 100 -
T 3 ..
$ 80 -
60 -
- From AGN #1 X From rod drop (NCA) 40 -
20 .
0 6 a 6 l0 10 20 24 Position (cm)
Ffgure 8. Coarse Control Rod Calibration Curve.
15
~
25 - _
Feb. 9,1982 Fine Rod Fully in 20 - 200C Critical at 20.4 cm fl 5
3 3 15 -
's E o m t-
{ 10 - /
~
2 /
/
5
/
/
c / i i i f 6 20 3 21 22 23 24 Coarse Rod Position (cas)
Cri tical Figure Sb. Coarse Rod Partial Calibration.
16
\
,4 '
2 d
n a
,2 2 e s
r a
o c
( .
)
ed ve
) rt
,0 m ur 2
c C e '
, ( s nn n oi i
o i t y t al r rl e bu s i f n l as I
,8 Cd 1
R o C d r
._ F o Ry t
ee nf
_ i a F s
,6 9 1
e r
_ u g
i F
,4 1
2 1
0 0 0 0 1
- 3 2 7 U 8 m >," > L M a T ,'t.N5 C
- l, ! ,!
s
- c. Channel 3 - Boron-lined Ionization Chamber Similar in construction to the Channel 2 detector, this channel includes a linear picoammeter as a monitor of the detector current and has scrams at 5 and 95 percent of indicated range (as well as at 2x licensed full-power).
The detector is physically closer to the position of the start-up source, therefore it is used to verify insertion of that source.
- d. Auxiliary Channel - Boron-lined Ionization Chamber Similar to Channel 2 and 3 detectors, this channel is an auxiliary monitor which can be used for highly accurate reactivity insertion measurements. This process is accomplished by adding a series current source (from the installed current supply) to cancel the detector signal.
This differential measurement allows current changes to be recorded with two orders of magnitude better resolution than from the detector alone.
- e. Strip Chart Recorder A strip chart recorder is used to continuously record the output of channel 2 and either channel 3 or the auxiliary channel. Provision is made at the front of the console to select the output of either channel 3 or the auxiliary channel for recording.
- 2. Safety Interlocks There are three safety interlocks included in the reactor instrumentation. If any of the three is tripped, a light is activated on the control panel and magnet current to the rod drives is deactivated (scrammed condition). Those interlocks are as follows:
- a. Shield water level monitor - float-type monitor, trips if water level is more than 6 in, below the top of the tank.
- b. Shield tank temperature - thermgstat trips if water tank temperature drops below 18 C.
- c. Earthquake switch - a small stainless steel ball is dislocated by heavy vibration causing the tripped condition.
l
- 3. Radiation Monitoring Equipment Radiation monitoring instrumentation available to the reactor operator includes a console-mounted meter and a portable survey meter. These and other such instruments 18 . _ _ . . _ _.
available within the reactor laboratory are calibrated periodically by the Radiological Safety Office of the University.
There are remote area monitors with automatic alarms s'
installed to monitor the Reactor Room, the building exhaust stack, the Co-60 cell area and the co-60 console area. All of this instrumentation is listed below:
- 1. Ventilation stack 0-10,000 MR/HR - Alarm 10 MR/HR
- 2. Reggtor room 0-10,000 MR/HR - Alarm 10 MR/HR
- 3. C nsole Area 0-10,000 MR/HR - Alarm 10 MR/HR 60
- 4. Co Cell 0-1000 R/HR - Alarm 100R/HR j All detectors with the exception of the one in the Co-60 cell are G-M type--the Co-60 cell detector is an ion chamber. All detectors can be checked by remotely
~
activating shutters that uncover installed check sources (Cs-137).
The detectors are monitored at the Co-60 control console. Alarm set points are adjustable.
Radiation Monitor RM-14 Eberline Detector: This is a Geiger counter for beta or gamma radiation detection.
l Range: 0-50,000 CPM Power: 115 VAC Application: This is installed in the reactor console for local monitoring.
Model E 400 Eberline j Detector: G.M. Beta, Gamma Low Range Range: 0-200 MR/HR Applications: Primary use, monitor reactor during startup and operation. Secondary use: lab survey meter.
l Model PNC-4 Neutron Counter Eberline j Detector: BF detector, moderator for fast neutrons 3
is 1 1/4 in. parafin wax enclosed in 0.03 in.
l cadmium. Reads thermal neutrons when detector is I
out of the well. Reads fast neutrons when housed in moderated well.
Range: 0-5,000,000 CPM Application: Reactor monitor - lab survey meter.
l __________ _______________
l i
19
I l
l i
III. Reactor Location A., Reactor Site The University of New Mexico is located in Albuquerque, New M xico. The location of The Univeristy of New Mexico campus is indicated on the map provided as Figure 10. The proposed reactor site is near the southwest corner of the main campus inside the city limits. Surrounding land is used primarily for residential purposes to the west and south, and campus of the University to the east and north.
The University of New Mexico derives its entire water supply from four (4) wells located on the campus. These wells are U.N.M. property and as such the University water supply is not included in the municipal water supply. The location of the four wells are indicated on the campus map (Figure 11). The depth and capacity of each well is as follows:
No. 1 (east of the Heating Plant) - 282 ft - 450 gpm No. 2 (N.E. of Physics) - 281.5 ft -410 gpm No. 3 (N.E. of Johnson Gym) - 414 ft - 900 gpm No. 4 (by Elec. Engr. Bldg) - 211 ft - 450 gpm.
The fourth well has not been in use since May, 1965. Virtually the entire Albuquerque area receives its water from wells tapping the water table of the Rio Grande Valley. The water table slopes diagonally downvalley from the bases of the Sandia and Manzano Mountains on the east and the Rio Puerco on the west toward a ground water depression or
" trough" about 8 miles west of the Rio Grande. The location of water walls and the associated water table is shown on the maps provided in Figure 12. As of 1961 there were a total of 77 municipally owned wells and a total of 45 non-municipal wells'within the Albuquerque area. In addition there were 118 irrigation wells in the area. The majority of the municipally owned wells lie within a five mile radius of the reactor site. Public utilities are supplied by the Gas Company of New Mexico and the Public Service Company of New Mexico.
Meteorolocv The Albuquerque metropolitan area is largely situated in the Rio Grande Valley and on the mesas and piedmont slopes which rise either side of the valley floor. The Rio Grande flows from north to south through the area. The Sandia and Manzano Mountains rise abruptly at Albuquerque's castern edge with Tijeras Canyon separating the two ranges. West of the city the land gradually rises to the Continental Divide some 90 miles away.
The climate of Albuquerque is best described as arid continental with abundant sunshine, low humidity, scant precipitation, and a wide yet tolerable seasonal range of temperatures. Sunny days and low humidity are renowed features of the climate. More than three-fourths of the daylight hours have sunshine -- even in the winter months. The air is normally dry so muggy days are rare. The combination of dry air and plentiful solar radiation allows widespread use of energy efficient devices such as ovaporative coolers and solar collectors.
ae
- FIGURE 11 ,
g an-Map of the Albuquerque Area A d
...~2 t e. T.12 N.
- iI .
I \ \ T%h.y't j q
'g \ ] g \ \ s. k.. g h g f, ; acc
%] *,, i h /g,*/,: jc 9/^ % c DA$M r / . .Seae ed P O * ; ,S M x n e%Q 'g . I
{ 'S N. ., !1t = # '#. ' : C' ,5S'N.N, -Q..T D ? E p'.Q%d:4,,
, >s nb{sk6%
- l- ae3ss ..% .ly>gantT r
% ... ww WQW,2 . ...
..,.d,,,*,,, .
.,/.f
,A
.h .) M.kWW
,g .. ,7 ..-- -
,,, s.g s'- ,_.,.
'N.
, ..p - g/9 . :. 9 W- .~-f Sps ,,.;p,.7-y%
jW^R MANtsey'A G
.A,.1;'E
-~~
N 'T f..? +#. .._$"pv, s
A.*>
0b,, ..
a,gee ./..Py i[ '
/(+i.6[m'- C. ~Dt '. ~~%~~G
- m5;; ; , . "'. ..
- * . r a'^78 iT g,
w f . "*'3 d Nf-#. .. Mf.d g,,
I gtt. .,, , , , , -
t ?.* ..J *$ **..fzt .
- n'g . % .. .# 4 ,. / %
- @Ig4 4.N.
?Wz':'.%my V e .a. .
M,. .f g- g,g',a -.'---
g , , '
" ;-',,,,;,W
..op, f i3,2 2., '- *' '- ,fwi ... .,' ;.; :'M- -
ads J. '
- h. g , s g sm g 4 .. ,7 4.
-s' . t p, i;--
.% c' c_c;-% A.ti"!".ed's~
_p ,,,
,. \
+' (
p.+ 3 fi ' -
, y .- , , f,. , ,
f , '.' - - . N , ,'.'r/ * ,i <
.v d' . r v .;r.-.;.; g.. -.r:. A ,;*.,..
.. .:-, /.
y I. .j. 1, ~}.. --.... y/.!,og . ,. ,.,. "*,h., p...
- J,...-- ; ;q...
- .
.i., _
N "
I
.=:>-...- .
'~J ~ .:.:. .. I* II N e N_ M .c;..{/j ~O;;:-%."-
-*~ ..'- $ -- l , :-c::'", ~. . ';.c~m'.% %.%
W* ,.f
-} !: . l'.-
. .j K *
.a.e.*="**
^ - r % E'.s.~ i
i N...ss,g-y a =-- sy Q **** W (*
.~2)% ,e
-) @ $e% p. ,~ df.* V.
.g ..; o'Wo - p q L-(*-
a
? -
h1
-$ :.W y,=h.Mk -
Y -~""- -
, '! . 7/f,f. "l,Wi !^ ' ~;e'~..;'-
'.zy.# = q ~,. g
- ~ . -..m
- ; ;;
^
t . - ,- ~ . , j .- . .. . : . -
- . l
-w.', ,
s, y AY. $
.,, **, t-g,,,,-s.,
,*.e ** "**---"
- .(n .1,g,l(Y
,,,/ ,e
.L _
~-
~
sf * .h h, 5 ~~ .S ~. ,,.. ,
~ .*' .
N .
. - s.- ,
p .,,
(~ \ -~ s o. 9 . "
[ T ' [ .m ,.N' T^ .-
c ;
.\
g
~
_' pm%[~-I f! L;. ' -.
. . . m h '" [, ..co.
'="'g
,2 z.;'
/-"
f'R)h,./
- ,/ - ~~: #
,)
- y. y, ' @ W. -c , ..s -
i >j l
.T8g! @* ' Y 'i 2
,_ , = -;'~.*r:Ec.u', ..
p _, t }$-
i,, r---w-1,,',, ).% /~ ' " * ;
M .L. :. :. tw unrviesirr or wew anco
.h' I ei . 'k' . . . .hd_
- =='". '7
~
L 8 .c3'/;,
. -t;:: .,,,
~""
o 3 h -*lT'i %
Y, .
's 8k M %g::;igt
,h s .:
Q rWrwg ]$*.-g gf ::r
-i; A x N b u=-g!!::::t L .- N r _ ' -
T ION
- p-'herew )" .i 6 - -
- f-g:a -
1@{'~~,~m'%= : g 1".!. g#' ' ' q t 's Ati
~$ 9 Q
.r y.%'r =.yl'* p -<-.s '
~d- ~
'C.V .:g--
, .TJ - #
Nh.s r:i r..... A
-7._ m. Qs .- . - . .
- l; r 'e.,.,,
0 y/<g -'.EEy ";hqi .f.7. M 4 11 ==
E
,,m.
ea--v:c,.r~s-
.a, ,-=-w-=. "
_" iPe 4 9 ( )"'x %s . 4.
./,, t.g. .
.: . se,, .
3
' l ~'- "% D.**
l *Q ,
-.:> ~ g ; g.y. -,.d .V ' % ' , j 'L
~ .
9y...i,.. j,<in p .., a s e_ m .
1/. .
. . 7. .
}{_("' " . & nl so. ? _ **
,,' . ~ . . e? .D *y*op.n
, ,, l_ h.-
O I / _L'l p'%-&.$
$$~;&
.--1,.
.5 t- r ,,. =
+*--
kh5
- A'"ly,[.:x-?.k' 7., .2 2 a :P -
y, 7:J L' C i x' igy N h5l
.v,.-
, . l'l zhn .
it
+
W
~C&WY,n;Y,h:
- m V-k;/ smo
/ G.v..'.
- v. iI
.k.?
~-r
- m. sra a n y . ' O # .:f
--qw,u s'(
',,=^._,
F.f- .--e <.0:-- .- .'._
T9N.
i
' s,.,y; i .
gs . . . J,.~ .T,W'Ja
_3,a. a,.T 3 p . .. .-~ .....
.. . CM. -- i .. t
. . .O l I
_- M
. ._ _.,._'.1;g ].: ,'.-,Id,r '\ N.-.)';."' i~
s -
- , atscastar g a,
" th'
.. .a -%-"
. Z \.s.i " d~.
~.
yg1uu=
- .s g. V. % ~~ +
F '~ w
,'Q
- ,. \
}
3 h. , b ? M h+e 3, ' I Y..
r i l T."k..[
h 4J ya
/
peg
^ ur p* R.3 E. ro ci n,e y
\
i re so wrer.n, s
A re no -*it R.4 E.
nos ar
+
R.2 E. re .orr.us. os re nier re tu .o<< n.ar. or o.rc o, ,,,c.noe -ALBUQUERQUE w s..ie ,4., .,1 inch 2 uit . .ca, iou.o ca. im QUADRANGLE s...e ca. im
,o , ,
- ~ ' - ~ ~ - - '
C* 1 * * * ~ 5 ""' _ ' C. ea s e.,.U S. C .e .
sae t
+.ne S.=.,:. U. ..S. 6 -de,=.a.s.
FIGURE 12 Water Wells and Water Table near The University of.New.Kexico I ; . . ..
. n.
au f
y .
- r .*.-<*-
N N
['$.12;--t4[.gpHdh 4,-
shj
' )[f.' ;.,,j '
\ ,% '
. .i . . .R ElC ?.4 ',/
& '~~5 if ?lI 8 . .
~
jf
/ b, 1,. g,.
s .:.... a m- . w:. .r,,,wn.
' / !' .l .
/
- e j' t -. 4 -,n e,n~xo N n .-
.p N A7'
/ 4*1(ct.r.0. j.
/- ~
, y. .:s
, - ~ ~ ~ - - ~ ~
.)
y/: Q. 2x.1f.:plg
- yq. Q:; ,P ' ,'/ .
i ,Gl, ' : '-
jj ' . . .)
~
9 hN. v
./ 't
/ p;:_
[//pg.f.f.fdN_' ., , ..
i s .
- ]! %
/,f ,
4W
&jks.d % ' 'AJfDi hNg % Ni v tMf av '. _
Z-
+.
R v.\. ;- s0 \
s c- --~+
w! A l t'[ / -
" ~ '
-b.,
k.
W hf ?
aq?g. 3 (~~- >
v uv.c !k. ;/grx gm. .;ma , = . _ .. .
MOD thow'aig 10Cotient Of etfit md springt 014 &pths le w0tef h Ibt toutherrt holf of the Albuqwtfqu4 Orte,'
bef Bernorato county, 76, pen:<o. _ __
Precipitation within the valley area is ed2quate only for native ,
dasert vegetation and deep-rooted imports. However, irrigation supports successful farming and fruit growing in the Rio Grande Valley. On the cast slopes of the Sandias and Manzanos, precipitation is sufficient for thick stands of timber and good grass cover.
Meager amounts of precipitation fall in the winter, much of it as cnow. Snowfalls of an inch or more occur about four times a year in the Rio Grande Valley, while the mountains receive substantial snowfall on cccasion. Snow seldom remains on the ground more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in the city proper, however, snow cover on the east slopes of the Sandias is sufficient for skiing most winters.
Nearly half of the annual precipitation in Albuquerque results from afternoon and evening thundershowers during the summer. Thundershower frequency increases rapidly around July 1st, peaks during August, then tapers off by the end of September. Thundershowers are usually brief, cometimes produce heavy rainfall, and often lower afternoon temperatures noticeably. Hailstorms are infrequent and tornadoes rare.
Temperatures in Albuquerque are those characteristic of a dry, high cititude, continental climate. The average daily range of temperature is relatively high, but extreme temperatures are rare. High temperatures during the winter are near 50 with only a few days on which the
. temperature fails to rise above the freezing mark. In the summer, daytime
' maxima are about 90, but with the large daily range, the nights usually are comfortably cool.
The average number of days between the last freezing temperature in s,oring and the first freeze in fall varies widely across the Albuquerque matroplitan area. The growing season in Albuquerque and adjacent suburbs ranges from around 170 days in the Rio Grande Valley to about 200 days in parts of the northeast section of the city.
Sustained winds of 12 mph or less occur approximately 80 percent of the time at the Albuquerque International Airport, while sustained winds greater than 25 mph have a frequency less than 3 percent. Late winter and spring storms along with occasional east winds out of Tijeras Canyon are the main sources of strong wind conditions. Blowing dust, the least attractive feature of the climate, often accompanies the occasional strong winds of winter and spring.
A table listing monthly and annual normals, means and extremes of temperature, precipitation, humidity, and wind is produced as Figure 13.
This table is reproduced from the 1984 Local climatolecical Data for Albuquerque, by the U.S. Department of Commerce, Weather Bureau.
Geoloav and Hydroloav The Albuquerque area lies in and along the Rio Grande Valley, a long narrow structural depression bordered by uplands - a rift valley.
That part of the Middle Valley in which the Rio Grande flows is underlain 23 ,
FIGURE 13 AtaUcutRaCE. stir iscxico PRECIPITATION (inches) i YEARI JAN ; FEB ! MAR i APR l MAY !JUNElJULYl AUG l SEP ! OCT l NOVI u DEC Q.22
'ANWAL j e.i' 0.5J 4.JJ 6.60 I.JJ 8.14 0.06 0.89 0.04
-l 1955 O . Tv 0.C2 0.3J 0.03 0.00 J.06 0.43 1.49 C.18 0.62 'O.61 4 195b 0.46 0.49 ? i 0.04 2.48 1.32 7 2.59 1.24 0.32 1957 0.76 0.59 0.52 0.38 0.35 0.14 1.74 1.34 1,72 0.37 1.35 10.12 81958 0.21 0.27 1.71 0.62 0.43 0.22 0.36 1.70 0.07 1.85 'O.14 0.73 0.42 0.43 0.80 0.78 2.79 1959 0.17 0.04 0.56 2.88 0.07 0.39 d.12 r
0.34 0.44 0.19 0.71 0.91 0.47 0.78 9.97 1960 0.38 0.73 0.01 0.11 2.70 1.69 1.04 0.47 0.48 0.65 5.39 1961 0.23 0.10 0.61 0.71 0.75 0.61 0.51 0.18 0.07 0.01 0.19 1.24 7 r 7.4*
1962 1.01 0.11 0.03 0.11 1.43 3.00 0.63 0.76 0.29 1963 0.29 0.24 0.55 0.14 f 1.87 0.98 1.57 0.04 0.21 0.49 7.J4 1954 0.07 1.12 0.t3 0.61 0.J5 1.42 9.J1 1.65 1.18 0.89 0.33 1965 0.47 0.60 0.49 0.49 0.11 0.99 0.68 1.04 0.54 0.09 0.01 e.d1 0.42 0.04 0.02 1.66 1.63 1.06 0.56 8..'
1%66 0.30 1.71 0.61 3.30 0.79 0.18 0.15 1967 0.01 0.44 C.J5 7 0.04 3.33 1.49 0.30 0.12 0.59 0.92 ? 0 . o .'
1968 0.01 0.*8 1.48 91 0.99 0.05 2.37 0.01 0.72 10.56 0.C8 0.41 t . .'6 8.31 0.59 0.94 0.95 '1.08 1969 0.34 2.24 0.79 0.25 0.08 6 28 1970 7 0.2* 0.42 0.05 0.33 0.40 i.22 0.87 1.44 1.:5 0.67 0.23 1.40 l J.05 0.03 0.78 0.16 0.02 1.05 :0.
1971 0.27 0.21 0.18 C.55 1.00 2.*3 1.00 3.09 0.69 0.36 27 59 1972 0.12 0.12 0.08 ' 7 1.37 1.60 1.19 1.13 0.35 0.08 0.0J 1973 0.85 0.33 ? 2.10 O.91 0.66 0.22 0.79 1.56 1.*6 0.38 0.51 a.iJ 1974 0.58 ' O.11 0.85 l 0.14 0.01 2.40 0.28 0.28 f . .P 0.'s5l 0.10 0.66 1.43 1.40 1,66 7 0.20! 5 *. ' *:')
1975 0.26 0 . 's 9 1.32 0.73 C.45 0.03 0.24 1976 0.00 0.46 0.09 0.3t 0.82 0.60 2.28 0.78 0.76 0.42 0.
- 3 i 1977 0.99 I 0.?J 0.63 f.07 0.to 0.04 l 0.69 0.59 1.22 1.00 0.76*'O 9*
0.54 0.05 0.49 f.05 0.24 2.49 1978 ' .32 f 1.02 0.24 2.48 1.02 0.80 1.53 0.40 0.27 0.91 0.67' *".J5 .
1979 1.07 ' O.62 0.14 1.63 0.09 0.30 0.7J 4.5*
0.60 0.56 0.01 0.0S 2.61 0.37 *in 0.87 0.58 0.60 1.43 0.00 1980 0.53 0.35 1.07 1.68 0.41
- 1931 0.05 0.67 0.80 0.30 1.09 1,34 0.26 0.60 0.?9 .;'
1962 0. 32 l 0.20 , 0.64 0.05 0.52 0.09 f.32 0.27 0.91 ' 20 0.44 0.42 . * *e 1.10 g 3 71
- 0.6 s I c.02 0.32 1.21 0.55 .
0.63 1.J4 12.08 1903 0'.16 0.48 t 13 2.70 1.13 3.04 1984 0.33 , 7 0.62, C.50 Reeced 1.36 0.52 0.33 0.43 0.46 d 15 Me8n 0.40 l. 0.37 0.45 l 0.53 0.62 ; C 56 t.39 see eer eene t.ones on % sa.
1 n2e u 2
AVERAGi[ TEMPERATURE (deg. F) ALBUQUCRQUE. NEW M:XICO APR MY ' JUNE'J'JLYl AUG 1 SEP ; GCI NOVlOEC A W AL YEAR!JAN FES MAR n.+**~ *T *3 :e.s u.8 .:. , a5.e C.WP:w- ~Y M5 s n.s s 44.5 7. H. , :. 9 ,
fe.J 74.t 60.3 , 41.0 76.3 t iti.
.- 42.' s n.c i 49 2 55.1 8 e v.6 3 7a. ? i 79,1 4.4
- 4,0 70.3 56. e
- 40.J :s t . ! ' T*1 l
1957 3*.9. 44.1 47.3 i . 2.
- 6 .*: 7 4. ! ' 79.6 78.*, 69.2 56. . 46.0 42.4 , 5- #
- c 958 f, n.e l 4.1. s . v.0 4 u' 6 es el 48.6 .2 70.6 56.8 u., u .2 i n -
15.,3
- 3. ; n.5 ; 45.3 : s7.0 ; .5. . 77.0 , 9*.1 n59 78.4 7* 8 : 56.5 46.5 33.93
- 11. 0 ' 36.5 1 49.1' 14. ?'.9. 64.7 I ?6 6 l 78.7 75.2 65.6- 56.8 40.3 34.1 6 55.5 e'960 .
1961 13. 9 t 40. 6 g 47.0 5e e5.
- t ~5. 9 e 76.7 16.' 46.9 36.9l Tv.3 1962 !. 15.6 1 42.3 ' 41.2 *e.t i 64.* t2.? ! 76.3 ??.m *9.4 72.? 6'.? 45.7 S4.64 ' * * .J 29.4 ; 40.5l 45.2 5 7. ?' 69.4l 73., 61.4
- 75.9 4J.7 38.5 G.5 i
196J 1964 21.1 41.5 St.7 65.8 l 74.6f78.2 76.8 69.3l59.J 4 t# . 4 '1* .6 I 58'. 1 1965 e 36.8 .
l 30.0 ! 39.4 44.6 54.e 61.7l 61.4* 77.9 79.8 75.4 75.7 66.6 69.4 58.0 56.6 s es . ? 34.3 . 4%.4 tith ' 19 1 31.2 45 t '
54.4 67.2 72.8 l ?4.5 68.4 19 2 J6.1 32.4
- M.*
'967 '
33.2 g
42.5 i 52.5 ! ?*.8 63.9 * ?' 5e 7*.2
?6.1 72.4 48 0 53.3i 42.8 Jo .1 ' *tt.5 '
g 46.7 i 13.4 62.7 75.2 1 53.0 41.4 3 '+ . ' t ..e 1968 16.6 . 47.3 %e.2 79.0 70.0 1849 36.0
- 14.5 4' *I $7.4 73.6 g 40.2 36.4 ! N.,C 1970 34.5 ' 44.'
47.*!* 81.5 f.6 . 2 72. ? , ??.6
?) # *8.1 77.8
- J.4 67.5 vm8,9
.a 52.6 93.9 44.5 5.2 Jf.' ' ': . '
18 *j s .
- 1971 33.6 ' 42.f 39.9 l 53.3 i et.?
ed.C ?3
- 76.6 ?4.1 **6 . 40.t 33.0 ** d 1972 M.t 44.T U.6 ; % . '? l6 62.7 78 4 '9.0 47.6 53.4 4 4 . is J! .0 i 45,9 ', ac i I (3.2 ?).5 58.1 45.0 u..
1973 1 31.8 eq.5 90 ' 77.0 7J . 7 , 66.1 4!5;3 1974 ) 3 3.e , 3*.9 9 12.8 l 96.4 j 6t.6 1 73 2 ' ,
- ti . 8 ~6 t i 66.3 86.3 42,6 3'.
19*5 30.8 1 26.a 48.1 1 41.9 ! 64.0 S 3. ' ; 40.6 33.0 Y4.?
41.1 44.3 ; 54.6 ' n2.8 l
73.4 I 77.0 75.0' 7? 4I 69.4 Se 9 : 46.J 40.4 '. i e 19*6 33.2 ' ed.; 7 5 . 5 >' 01.4 76.6 47.5 34.J>
6
's ." J 4
19?? 2?.6 l 40.* 43.2 i S.? 75.5 ?5.5 69.1 60 3 1970 36.8 3*,3 f 0.2 3 57.? 63.5 77.1 72.3 ut.5 41.0 37 *l 97.2 i
1971 32.9 4'.t J5.4 l 86.9 63.9 73.3l 80.6 77.4 54.5 43.9 *?.4 am.t l 82.1 61.1 77.2 e2.7 69.9 JJ.5 40 t 'I SG &
1980 40.2 44.2 64.9 77.0 79.8 76.4 69.7 95.7 47.0 34.4 '.=2 1981 10.0 42.9 46.; e 59.0 74,8 79.1 77.4 69.5 54.8 J2.9 34.7 Se.*
1982 35.9 39.4 4 7. 4 f 86.t 63.0 73.4 58.J 45.I 34.7 I 46.4 50.2 63.0 73.4 80.4 71.4 51.* 43.* 35.6 *ce.0 1987 35.0 69.1 73.6 78.9 75.7 ,68.8 1984 34.1 40.1 46.8 52.8 56.7 43.9 J5.3 %5 0 Recoed 63.8 73.5 77.4 79.3 68.5 47.4 4 '+ . d Meaa 34.5 39 ? 46.3 54.8 99,3 08.6 82.3 71.0 57.5 47.1 53,0 ' 60.8 l g9.9 79.0 e 89.1 54.7 42.4 30.3 23.0 48.8 l
Pne Man 22.0 26.3 31.9 1 39.7 48.5 1 57.9 63.5 61.8 See neferencePage Hetes 4G ca Pace 60.
i i
) .
24
T with up to 120 ft of recent alluvium and is called the inner valley. The alluvium consists of unconsolidated cobbles, gravel, sand and silt and is highly porous and permeable allowing relatively free movement of water and yiolding large quantities of good to fair quality water. Beneath the clluvium in the inner valley to a depth of at least 5000 ft. is the Santa F0 group, similar to the alluvium. The Santa Fe group consists of unconsolidated to loosely consolidated gravel, sand, silt and clay with come interbedded volcanic rocks. The Santa Fe group yields large qucntities of water to wells.
The Sandia and Manzano Mountains border the Rio Grande Valley on the east. The sloping surface of the valley fill from the base of the mountains to the Rio Grande is referred to as the east mesa. The slope of the east mesa is about 250 ft. per mile near the mountains; near the river the slope is about 20 ft. per mile. The distance between the base of the mountains and the east edge of the inner valley ranges from about 3 miles in the northern Albuquerque area to about 9 miles in the southern part.
The inner valley is relatively flat and ranges in width from 1 to 4 miles. It is separated from the east mesa by a bluff. The University of NOW Mexico campus lies on the east mesa about a mile from the inner volley. The east mesa is underlain by the Santa Fe group to a depth of over 5000 ft.
A series of cut terraces parallel the Rio Grande on the west. A broad upland called the Llano de Albuquergae about 600 ft. above the river bor.ders the cut terraces or. the west. The Llano together with the cut terraces is called the west mesa in the vicinity of Albuquerque. The Llano is some 70 miles long and 8 to 12 miles wide, sloping southeastward at about 50 to 100 ft. per mile. The majority of the west mesa is underlain with the Santa Fe group.
The Santa Fe. group and the alluvium yield water of the acceptable quality for most purposes. Most of the water has a specific conductance of less than 1000 micromhos. In the alluvium of the inner valley water of poorer quality is found at shallow depth. This water is mostly that added to the groundwater reservoir from irrigation return. With increased depth the quality of water is better and approaches the quality of water present '
in the underlying and adjacent Santa Fe group.
The water table slopes, and groundwater moves, southwestward from the Sandia-Manzano Mountain front and southeastward from the Rio Puerco, toward a groundwater depression about 8 miles west of and roughly parallel to the Rio Grande. The water table in the Rio Grande's inner valley slopes southward and resembles in cross section a horizontal shelf on the southwestward slope.
The groundwater reservoir in the area is recharged from precipitation, from perennial and ephemeral streams, from irrigation cystems, and from water applied to the land.' considerable recharge occurs n0ar the top of alluvial fans near the mouths of many canyons in the Sandia and Manzano Mountains.
25
The block diagram in Figure 14 shows the topography, geology and water table in the Albuquerque area.
Seismoloav The following data were obtained through the courtesy of Dr. Stuart A. Northrop, State Collaborator for New Mexico, Seismological Field Survey, U.S. Coast and Geodetic Survey, The University of New Mexico, Albuquerque, New Mexico. References (14) and (15).
List of earthquakes felt in or near Albuquerque (Rossi-Forel Intensity Scale),
1893 April 8 A Belen Shock (Intensity VII) was felt in Albuquerque July 12 Three shocks at Albuquerque, one of Intensity VI 1906 July 16 A Socorro shock (VIII at Socorro?)
was felt here Nov 15 Another Socorro shock (VII to VIII?)
felt here 1918 May 28 Severe shock of shallow focus at Cerillos (possibly VIII to IX there) was felt here (IV).
1930 March 23 Slight Dec 3 About VI Dec 4 Slight 1931 Jan 27 Slight Feb 3 V Feb 4 VI to VII 1935, Dec 12 to 1936 Jan 4 The Belen swarm with 81 shocks on 24 different days at or near Belen. Of these, seven were felt at Albuquerque, as follows:
26
~
n
&3Bd as *Demasai, arte.snmad o .a.
1 _
-e ,
s a t
f
[
[. 2j . :
.:e '
2 1 .
cm
- s. .*,
c ; , * * -<..- ! 8.
-- i-
. ,; ,.. u .c
<; .- ) -
l} .' ,: ? . .,. , . . , . . . ' ,
'a
. , .4 ":. '-. 24
. .o 4 ,r 's- + * , .., .*
- 4 * . .., .w, m. gg >g F
'T t
,* 4' p.=
- 7 a.e e;ge *,, -* **a .,'. , a, J
,o a I
=
,.. ... . ., ::: ~... ".::
+ . ,. _.
. i.
.., , r.. ..
m
. 1, _t.,. n,
,p.3
- a. .s
... .. .... y.
~u.:.'
.se,*.
- u. ~
p' -
y..:. .
. 1s 1l:
l *= . M.)' % : :., 4%R.WE
. M.h ..-::- uR::?:~
!~ s3 g~
s
. .. e, a: . . .r .
-. . A. . . . . -
e-.
.,, . . . .... .. ..i .
.i.. . . - _
.. : .* . .... .. . . , ....m . , .
~...
~ ea
-y }: Ij.-s
- . - -.l.l 8- N.
t!.
o g .
- q. . * .."
- -l. %. .-
I j 1.l s. a.
a w u a s
t . l. 1 ,
p: . **.
..l.* ' , . * -
g (f t,]}:L: :.
2 o
- .l.. ;,s.j j e, I t :.
@I j. .s tjEg 3 n
- g
- f,,, i. .
,- .- ;. I .
c= 5 y ,.. . . . . 3 2 b Aj. t- j$3
) .. *..? .*. D U
, . o. f,.l..**.. ..= . *
.. l. .. .l . $.2 gg,,
2 {:..
<w
.c .
j y31::
- 4' i 3'.. *
,y. , . * ,
(*.* .. g.
s *4
- 3-
. A }A Lc a a g
/' \ .s
., g
- f~~?; = .% an c
. f. .,.. y *. .....
5 -
~
w -( ! ..
a >.
}
gg '
- , .*:,. u,,,,,,.
uma n
u u Is \ r. ..w L *.. .. 'l*.* .
m,as re c
,8, - 1;
.s ./ . . . * . l*l- . = . .** l:.
- i. ,
. pe ee g,,, , ,
..r .. :,i . .o
., ,.,.. J '. .. .i '... ..** . i,*
.: 3 *
. 2:3 w Ie. T .r ,J:.... . . . .- .p .. ;:2 . ...
- =
o.
}s! .::
e
- , - . .o.
' i l .i ; 1 , .=:
1:4 .
- N
. -,/
. . ?* .
.l f.**
. .e
... , ; I }31a. - ?;. .* 3 [ 17 l.3..)!
_ .e. . . : :
E* **
.v .. 13.:.
- nn n.u
,7 .. :. . . ,..
. . ... ; ... ...i . , 351.:5. a j : .: 3 p=:l [* .
- s.. ;I.
3 :u.
- 3 4
- .g a c
(
- gni g t*i !r .!!.! a
{ P,/;,4 .: S c. ..p .. i t .-.i .
I ,* ,
us .: .
., . . . . ae,.- .:- i i -
.l . *.
d
, ;W. ,. . ..
,- > ct.
l,,. .
a .g i
. ., 44 .
- 1; . .*l.
l-
. :. . ' : .i;
. g ,,g ainet.posin
,. o .,
( i ,) , ;./ .
~ ...e .. .
,.,, e eu y
G:b;.
swe.h ,
p
. - c.
./ s. m., _3 Y,'~qs M,:Wg1ww@'N P
.. . . . , , - oc-
.m ,
.\' . , -
l , ... *
$e&o Iih wl 5/ $$*
I 1
,Yl E'
Q* lbfl.f'$'.A'I'.$b{hlh" ! -: .$? : * .a i
l )/
p.
.4
)
e 4./j r s
0
.&Nl - --fer . Ar . .
/
/
/
/
/
/
g
H 1 g K O
,ok
- 3 2 M
- / , **
I h y """ = '
/ 3 . o i ,, ,,,,,,4 ' 2; s e- . - .
.I :. . . 1. 1i 430s ne'penas49e ,7..~."
O a
i .
I l
27
}
Dec 17 Dec 28 -
l Dec 30 (most severe one felt Dec 18 Dec 19 here)
Dec 21 Jan 4, 1936 1936 Sept 9 IV to possibly V Sept 11 Three shocks of about III each 1938 April 13 Slight April 16 Slight 1947 Nov 6 Slight, in Sandia Mountains 1954 Nov 2 IV Nov 3 V 1956 April 25 Slight, in Sandia Mountains The Rossi-Forel scale of intensity is as follows:
I - Microsaismic shock: recorded by seismograph, felt only by an experienced observer II - Extremely feeble shock: felt only by a few persons at rest III- Very feeble shock: felt by several people at rest, both indoors and outdoors IV - Feeble shock: felt by persons in motion, ceilings creak and crack, small objects may move, standing autos may rock slightly V - Shock of moderate intensity: felt generally by everyone, heavy furniture may be disturbed, unstable objects may -
overturn, dishes and a few windows may break, VI - Fairly strong shock: general awakening of those asleep, trees and shrubs visibly agitated, many small objects overturn, property damage slight -
VII- Strong shock: overturns many movable objects, canned goods thrown from shelves, plaster falls from ceilings, general panic without much damage to buildings except ceilings and windows VIII Very strong shock: walls crack, plaster falls from both walls and ceilings, many windows broken; chimneys toppled, weak buildings may collapse 28
I' IX - Extremely strong shock: partial destruction of some buildings, total destruction of weaker buildings, people thrown from their feet, possibly some injury and loss of life X - Shock of extreme intensity: great and general disaster, extensive property damage and loss of life, fissures develop in ground, falls in mountains.
Updated information beginning in 1970 for the area within a 100 mile radius of Albuquerque was obtained from Dan Cash at Los Alamos Scientific Laboratories (LASL) . Figure 15 shows the calculated epicenters for the recorded earthquakes which are listed in Appendix B. Although 1,974 earthquakes were recorded by LASL equipment, only 2 of those listed wore calculated to have a local magnitude greater than 4.0 (they occurred on March 5, 1977 and March 2, 1983).
Democrachv The population densities around the Nuclear Engineering Laboratory listed below were calculated from 1980 Census Tracts Data obtained from the Data Bank on the University of New Mexico campus.
Radial Distance Poculation Area Poculation Density (miles) (sq mi) (per sq mi) 0-1 1,582 .61 2596 1-2 15,784 3.2 4928 2-3 41,551 11.98 3467 3-5 127,585 82.47 1547 IV. Reactor Building A. Laboratory Building The laboratory is a one story concrete structure with six feet of carth between one foot thick concrete walls on the south and west sides.
l The north and east walls are poured concrete approximately one foot thick.
l A floor plan is shown in Figure 15. The only outside windows in the' l
building are in the entrance doors. There are four entrance doors into I the building: (1) a personnel door on the east side, (2) a personnel door l
and (3) a double-width equipment door on the north side (center) , and (4) a personnel door on the north side (west end) which is bolted und not normally used. The roof of the building over the Reactor Laboratory is l three feet of earth between five inch thick concrete slabs. A portion of tho roof is five feet of earth between five inch thick concrete slabs to provide additional shielding for the Cobalt-60 facility located in the lcboratory.
B. Reactor Laboratory The Reactor Laboratory is located in the southeast corner of the Lnboratory Building in a room 20 x 24 feet. This room has two access 29 L
Og + ) hoo o + Oc .g o +o
$ o o eo
- o o o
"( e 9 o o .s % ** S* a N o o S N% o *3 E o N ( o, , o + .c o 7,o + g~
lg
- e ggg *g ,
efW o
- o O o,
o, o
8 , hs q 4
..* a o .! oo o h oog g o,, p -
S A
q o
- o%*
o 8 oo o, o Q o o ao *O" &*g ,
O o
+e o
b 49 -
o 9o o o, od_o p
0+
8 n D N,9E N SE N,fE l
4 tr 30
-__ =.=:_
i i
%% %% %%% %sNsss %%gsg gggggg g gg g g. g s g gN g g g\g g 4 Ts A % s ' =
s I >
- S - : ==
1 a
=
. .!. T.; s 3 3 =
E! E !g i !!
a A .
w, m ssv (t
k u ss si g
- l=.
=
O g
g < s rm ,s s .u ssms ss ss s Y , ,%
l u - .m 2e .
m 3DVWo15 220 *N W U m 30Mfl0S U" s +.wss a
_______. == =
E=5
'N 9 l i
==
.. E.
=
. .4
- a. ,V o :
.\ .es ,
c i*3 ,,)
y!
at:' . A.
( i
)3
=
.= '
i ,. ,,.m m, Q_.
aw a
l d N g >3 w
"" s < l 1 !! i>i i L_ "i ]y !
C
{ k'N ':N j ;
m.
! " .a GS h'
- .. "8 2 o
h!u d
.s Ua $
- e. OO no
- U l\ oV. s > ! :; '
l *K.sk ' N'N s &
l f s ,- ~ , , , , . . . ,\s _ m . , , s . s ,
- a n y ., a o
s s s o ....
M E s 3
- lu
. ;gg. g.. s. .,,. , ,
- : 0=
- , ! '1
^ 2
==
ou :::
- , + j=
5 nooW N33WOS y! NY g g
3 m__ _ _ _ _ __ _ _m_ _ _ _ _ _ _ g- .
e s
31
doors: (1) a personnel door in the north wall of the room, and (2) a double door for equipment and personnel access in the west wall of the room. In addition to having six feet of earth between one foot thick concrete slabs, the south wall of the Reactor Laboratory is entirely below grcde level. The east wall is essentially below grade level because of tho exterior concrete stairs which go from the floor elevation up to the ctreet level.
V. Safety of the AGN-201 Reactor Facility A. Maximum Credible Accident The total excess reactivity of the reactor is given by the manufacturer as 0.5%. For the purposes of a hazards analysis, however, it in assumed that an instantaneous insertion of 2% in reactivity occurs.
Because of its inherently low excess reactivity, the system could never ccquire this reactivity in the course of normal operation. It could only occur if improper materials were introduced into the. reactor. Strict cdministrative controls discussed in the next section will normally make this impossible. The placing, for instance, of fissile or fissionable material in the glory hole will be strictly forbidden. In this sense, the acsumed 2% in reactivity is admittedly rather arbitrary since anyone capable of inserting 2% in reactivity in the reactor is surely capable of inserting 20%. Nevertheless, the analysis demonstrates the fact that the reactor does not " runaway" following a sudden increase in reactivity.
The analysis of this type accident is given in Appendix A. It is shown there that this accident leads to a power excursion which is self limiting in about 300 milliseconds. The maximum temperature of the core never rises above 100 C. However, tests performed by the manufacturer indfcatethatthecorematerial, polyethylene, does not melt below 200 C. It can be expected therefore that such an accident would not damage the core.
As previously noted, various scram circuits would be activated as the result of sudden increase in the flux in the system. However, if for come reason these circuits fail to operate, the reactor would be shutdown by the melting of the fuse. This fuse is loaded with twice the density of uranium as the remai'nder of the core and would reach substantially higher temperatures than the core during an excursion. In addition, the fgse is made of polystyrene rather than polyethylene and melts at about 100 C.
Following the disintegration of the fuse the core falls apart which decreases the' reactivity of the system by from 5% to 10% according to the manufacturer.
It is shown in Appendix A that this accident would give a radiation dose of less than 1.1 rom to a person standing immediately next to the concrete shield. This dose, while far from desirable, is well below lcvels which lead to detectable medical injury.
B. Shielding Requirements for 5-watt operation As detailed in the amendment for 5-watt operation for Acrojet-General Nucleonics, dated February 11, 1957, and on file with the 32
p
- i l
commission in Docket 50-32, an 18 inch additional concrete shield wall is l cufficient to maintain sub-tolerance radiation levels external to the i chield when operating at 5 watts. Subsequent conversations with ;
Acrojet-General Nucleonics indicate that 16 inches of ordinary concrete chielding is sufficient. Thus, a stacked concrete block wall consisting of solid 8" x 8" 16" ordinary concrete blocks was assembled around the
- oxisting reactor tank when the maximum power level was raised to 5 watt in l 1969.
4 The essential features of the shielding are shown in Figures 17 and
- 18. The shield wall extends two feet above.the top of the reactor. Thers 10 no shielding over the top of the reactor, this area being a controlled i arca during 5-watt operation. Access to the skirt doors is by way of concrete shield doors mounted on casters with a maximum of 1-inch clcarance between the floor of the building and the bottom of the door.
The blocks are stacked in staggered layers (both vertical and horizontal stcgger) to elininate any straight-through penetrations.
The radiagion lgvels associated with 5-watt operation (peak thermal flux of 2.5 x 10 n/cm -sec) are given in Figure 19 as measured on
- April 18, 1985.
Assuming a dose rate of 0.4 mrem /hr as calculated by AGN as the i most severe case of air and roof scattered neutron radiation and 0.5 mrsm/hr of gamma radiation due to streaming through a 1/8" crack or hole in the shield as per AGN calculations, the total expected dose rate for j ths 16" shield (maximum obtainable) should not exceed 1.5 mrem /hr of nsutrons plus 5 mrem /hr of gamma for a total of 6-7 mrem /hr.
The measured dose rates immediately adjacent to the shield are too
- high to permit unlimited access. Thus, chains have been placed across the
, stairway entrances into the reactor pit and persons are allowed in the pit i only for limited periods of time during 5-watt operation.
The top of the reactor is not shielded, the measured dose rate at 5 watts will be about 100 to 150 mrem /hr. The top of the reactor is a high radiation area during 5 watt operation and, therefore, access to it is .
' controlled and strictly limited. Attenuation through the roof reduces the radiation level on top of the roof to less than .05 mrem /hr.
i VI. Reactor Safety Evaluation ,
l A. Characteristics of the System f 1. During normal operation, negligible amounts of fission
! products are formed within the core and a large part of l these are contained within the-UO 2 Particles.
l 2. The core and reactor gastight tanks are the primary and secondary seals which will retain the gaseous fission products released during a nuclear runaway.
33
y -
s'c~~) ...i y- 2+ f
.i< -
- t. '
I
- ..f A - Se. f4 . .
1 -
+ 1L.,, ') / o,.ct,..w.<., b..vut < blac. <- .
/Ing e.l Jr.n Dea.. e.
g ., /_/ / . S " t e "V. i t. " ( a . .) ,
l ,
<-> 7 .
. 7
.( q A h ' 3l (\]al\ cy al\ _& sicies). .. - - -
. g {i_
i . .
i- -
,5. _\ . .
. ,i . .: ..
1 8.(nom.h .
flavw.. r G:.9
- : 1
--t g.1,,c,, cl.,.j w. h.g ' '
L. :< < c.. . cc.g,k j -
O . .... O a aw_n- s, , i --
.g -
e o
n,(n.,) :
o- .- .. .
m
. g _.-. , , ,
~
3,N Q
' ,- - . ... '-~~, .
..- . ......i
.__ _ l - ,
q l i.
l .
./' /,/ . .
.) k
{
2
- - . 4
- H
.. , g
- s' t/3
.s
_ .v f
- C
. .s -
.ar b.,,3 o .,,
1 H N
+
~
l, I
g Si - . '
r--
9 .
l -
g _ L,
- u. --
t.
i I
i
. - e . t
. g '. . _j m .. .. . .
. . 4- J, .
- g .
t'1 .
8
-- j ke t
{ - -
i +_ g......> . T - - . . -
- n
~~'l.e .
o _ .
- C~=.
s.
- .)-l%i
.E $. I **
'_%..~
I
( *-) % o.
d M 20 e d.i a? a .
,t ""* *w
,O. ,f .
- 4
- g. s
,2 .
- =
.Y l
.4 o . ') ,." so 4 e
> 7=4 -
g
- Ck r *$ 1 - - < <f. :s c) se a]
. b.
')
! . a
_ 4 <
4-v t . .
.c.s o4 e%
a -
c-
- - --> Y_ _ _ . _ _ . _ : .- ,
t *
- I e* %e ,
V) *u .
- . =
35 .. . .. . . .
- ~- -. . .. --
FIGURE 19
. h, . W , , "2, 6_ _ ,
AGN201REACTORRADIATIONSURVEY Tirector.l:adicionical W.L. labor Sa f ety I April 18,1985 REMARKS:
DATE:
. . . F OPERA.TI0ft:
$URVEYED BY: _ h 8o ,,,< c/u INSTRUMENTS:
D a s o.v Jo s d e
_4,.,.. .
GAMMA Ludi um Model 3 GM - rAau N Eberline PNC-4 u t u N
f 5 watts EACTOR POWER: .
ADIATION SURVEY DATA:
- MEAR DATA ON DIAGRAM:
- nrem/hr 0Y bkgd*
. CONSOLE A2 mr/hr
/ R _c/mng C* 9 mrem /hr 3 S~ bkgd _
2 50 _c /m?ig_ mrem /hr Jr bkgd .
- r ' ' @
YELLOW LINE ON FLOOR -
5' _ mrem /hr eof _bkgd -
mr/hr_d.11 mrem /hr 27 bkgd 20' c/mN _
0 Y mrem /hr a' r bkgd @
'M c/mN _
o 2 'DE OF REACTOR TANK SHIELD
.?r mr/hr mrem /hr 0*r bkgd -
(?)
40 - mrem /hr 2r bkgd E
/S R c/mN 2r .bkgd L M c/mH g_ f _ l 2 r_ mrem /br " '
S
. N -
REACTOR SKIRT SHIELD W i
- 4. mrem /hr aar bkgd f _mr/hr D~ bkgd 2
_5 8< c/mNf _ /Y mrem /hr
/1 4 c/mNg 6 mrem /hr
- bkgd W
- 5. GLORY HOLE ACCESS
_ mrem /hr 08f bkg'd
/f_mr/hr
.bkgd 3=5~ c/mH g _d ?0 mrem /hr 2r bkgd..
I W_c/mH g _0 6 mrem /hr di
~ .
.6. REACTOR TOP CENTER
- mrem /hr 0 of bkgd 200 mr/hr_ bkgd ,
7 u_c/mN _ 9 S mrem /hr_ 2 5- bkgd 254 c/mN t- /25 mrem /hr :L 5- '
- m P./ths' (
SMEAR SURVEY RESULTS 3cnting Instrument Used Background cpm cr sults (net dpm) RS-9-p.
.---4-----./.. = . . . _
a ,
Console ,\.
Genera) Floor ~ ~
- 3. Thetemperaturecoefficientofreact{vftyisnegativoand y).
large in absolute value (~-2.5 x lo c
- 4. The amount of available excess reactivity in a normal loading of the core is restricted to about 0.25%.
- 5. The safety and control rod system is a " fail safe" design in that the scram signal opens the holding magnets, allowing the rods to be accelerated downward by both gravity and spring loading.
B. Causes of Hazards
- 1. Sabotage and Unauthorized Use of the Facility A well-informed saboteur presents a most effective means of destroying the reactor system. The main reliance must be placed upon the enforcement of Laboratory security regulations. The same is somewhat true for an individual who tries to operate the reactor without direct permission from the responsible Reactor Supervisor. By installing locks on the critical components of the system and by adequate control of the keys to these locks,
~
performance of an operation of this kind is made very difficult. It is, of course, assumed that any person on the reactor staff who has access to these keys is aware of his responsibilities and will never operate the reactor without authorization.
- 2. Accidental Operating Errors In general, accidental errors that occur during the normal operation of the reactor will be rectified before the resulting hazards arise. Interlocks insure that the proper procedure is followed during the startup of the reactor. Abnormal conditions caused by human error will automatically shut the reactor down. Scrams can be
- initiated by the following:
- a. Exceeding a maximum preset power level
- b. Placing the reactor on a period which is less than 5 sec.
- c. Lowering of the shielding water level
- d. Loss of electrical power
- e. Pressing the sensitrol reset button
- f. Reaching a minimum preset power level
- g. Disconnecting the electrical cables to the safety and control rods 37
. h. Pressing the manual scram button.
The worst possible human error that can arise is the accidental insertion of fissionable material into the reactor. Entry to the core can be gained through the top of the reactor by the removal of the thermal column tank or through the 1-in. diameter glory hole.
During normal operation the fuel loading is fixed, the thermal column water tank is installed, and the top cover plate is locked in place. Hence, it is extremely doubtful that accidental insertion of fissionable material would occur through this entrance. The glory hole is normally locked in any of three positions:
closed, open, or closed with aluminum plugs in place.
The accidental insertion of fissionable material into the core through this entry is therefore possible only when the lock is left open. The unavailability of fissionable material in the general area limits the chance of this occurring.
- 3. Equipment Failure As far as possible, all electrical and mechanical equipment has been designed so that an equipment failure will cause the reactor to shut down. In the event of an electrical power failure, the safety and coarse control rods, which are held in place by electromagnets, will be rapidly ejected from the reactor core. Any electrical cable failures will also scram the reactor, since each of the safety and coarse control rods has a reactivity worth of more than 1%, any one rod can shut the reactor down under normal conditions. .
There are two flux indicators which monitor the power level of the reactor. Each is connected to a sensitrol relay for high- and low-level trip purposes. The reactor ,
can be scrammed automatically even though as many as two trip circuits fail simultaneously. If all the trip circuits fail, a shutdown can be initiated by actuating the manual scram.
A major problem would arise if all the rods failed to scram when the reactor power was rising. This event is very unlikely because of the " fail safo" design of the rods. The resulting hazards are analyzed below in Part C.
38 l
r C. Hazards due to Accidental Operating Errors and Equipment Failure ,
- 1. An increase in the radiation level can arise if the l shielding plugs and covers are not in place. A visual '
inspection of the shielding is required in the checkout procedure. If the operator's inspection proves inadequate, the area gamma monitor will detect the error.
- 2. If the reactor is operated without water in the shielding tank at 5 watts power, the radiation level just outside the reactor tank will be about .1 mram/hr of gamma rays and about .25 mrem /hr of fast neutrons.* Although the radiation levels are above the permissible level, the hazards are obviously far from acute. It is doubtful that the loss of the shielding water would not be detected during the checkout procedure. A shielding water level switch, included in the interlock system of the reactor, prevents operation of the reactor when the water level has dropped.
- 3. If the control rods are accidentally inserted after the operating power is reached, the power will rise with a period of less than 15 sec. The reactor would then scram after a preset upper power-level on the logarithmic channel or count rate meter is reached. If the scram mechanism did not function properly, the reactor power would rise until the negative temperature coefficient
. reduced the reactor to a "just critical" state at some high power. When the rods are fully inserted, approximately 0.25% of reactivity is placed into the system. Since the_gemperagure coefficient of reactivity is about -2.5 x 10 a k/k/ C, the equilibrium temperatgre reached at the higher power level will be about 10 C over room temperature. This will correspond to a fission rate of approximately 10 watts, a factor of ,
2 above the normal operating power.** The radiation level at the least advantageous position adjacent to the ,
tank would be approximately 80 mrem /hr. This radiation is not excessive due to the additional concrete block shielding. .
- A.T. Biehl et al., Elementary Reactor Exeerimentations (Oct 1957),
- p. 21 & attenuation from additional concrete shielding
- ibid., p. 99 l
39
-.---e-----_m--.- ___ _ -_
m ,
D. Hypothetical Maximum Accident The accidental insertion of fissionable material into the core through the glory hold could produce a major accident. The hazards involved would be dependent upon the amount of I fissionable material inserted, and the insertion speed of the material. The hypothetical maximum conceivable accident occurring, which could hardly be called an " accident", would be the insertion of 20 grams of U-235. The v lume f the 3
glory hole through the core is about }15 cm .. Typical fuel loading of the AGN is about 0.15 g/cm so the glory hol.e in the core area could contain about 17 grams of fuel. The reactivity worth of a gram of U-235 ranges from 0.1% at the core centerline to 0.036% at the edge.*
If it is assumed that the average worth of a gram of U 235 is 0.06% and that it is possible to insert instantaneously a reshaped fuel plate, the induced reactivity will be approximately 1.2%. If a natural uranium rod was instantaneously inserted into the core, the induced reactivity would be about 0.93%. The accidental insertion of either of these materials seems doubtful, since they would first have to ba reshaped to fit into the glory hole. However, their induced reactivities do have a bearing on the maximum l reactivity that can be put into the system. As discussed in the next section, a 2% step increase of reactivity is chosen to determine the hazards of a nuclear runaway.
E. Evaluation of the Hypothetical Nuclear Runaway l An evaluation of a nuclear runaway accident in the AGN-201 l Reactor has been made by the Aerojet staff. A 2%
instantaneous step increase in reactivity was arbitrarily chosen. As seen from the previous section, insertion of this magnitude of reactivity is within the realm of possibility and should adequately describe the maximum power ex'cursion.
Two assumptions are used as a basis for calculating the power generated in the accident.
- 1. At time equal zero, an -2% step increase in reactivity is inserted with the reactor at 100-mw power.
- 2. At time zero, the energy in the core is negligible compared with the energy liberated during the accident, and there is no heat removed from the core during the r excursien.
oibid., p. 99 40 ,
p Some of the pertinent constants used in the calculation were:
~4
- 1. Prompt neutron lifetime = 10 sec.
- 2. Reciprocaloftheaveragemean_{ifetimeofthesixgroups of delayed neutrons = 0.1 sec 3.
Temperaturg/goefficient
-2.5 x 10 C. of reactivity =
- 4. Specific heat capacity = 0.52 cal /gm- C.
3
- 5. Core density = 0.92 gm/cm ,
l The time-delayed behavior of the neutron density, including
, one average group of delayed neutrons, is considered. A numerical finite difference solution of the three nonlinear differential equations (for neutron density, precursor i density, and temperature) yielded a value of 75.0 Mw for the i peak power at time equal to 140 ms and a total energy released of 2.41 mggajoules. The resulting average temperature rise i was 100.7 C, and tge temperature' rise at the center of the core was about 150 C. The total dose to a person standing
. next to the reactor was calculated to be about i rem. The l prediction that the core does not melt and that the fission i products are contained within the core and primary and secondary containe55 15 r**5 "*bl*> Sinc
- Polyethylene does l not melt below 200 C. The power excursion is self-limiting because of core expansion due to the temperature rise. This is strongly dependent on the magnitude of the temperature coefficient of reactivity.
e 41 L
i APPENDIX A A.1 Safety Considerations during Nuclear Runaway To evaluate the safety characteristics of the AGN-201 Reactor, a nuclear excursion resulting from a 2% instantaneous increase of reactivity is considered. The reactor would have a period of about 10 ms. The excursion would last from 200 to 220 ms, at which ting the average temperature rise of the core (approximately 100 C) would be sufficient to stop the reactor because of core expansion. fhe temperature at the center of the core would rise to about 150 C. Since the fuel material is exposed to about 5 megarop of ionizing radiation during fabrigation, the polyethylene will not melt below about 200 C. During the excursion a peak power of about 75 Mw is reached, about the total energy released is 2.4 Mjoule. It is expected that all fission products released would be contained in the core and reactor fluid-tight metal tanks. To insure that the system does-not remain in a near-critical state (iftheregsalsoafailure to scram), the thermal fuse which melts at 100 C will drop the lower half of the core to the bottom of the core tank, so that the reactor becomes subcritical. The total radiation dose to a per. son next to the reactor would be approximately one rem. If a loss of shielding water preceded the excursion, personnel next to the reactor would receive an exposure of about 200-300 rem of fast neutrons.
The total elapsed time between a neutron-induced signal from an ion chamber and a 2% decrease of reactivity from the resulting scramming of the safety rods may be as long as 300 ms. This breaks down to about 250 ms for the electronic circuitry and 50 ms for the necessary safety rod travel.
Periods in excess of 30-50 ms will be adequately arrested by the scram system. Periods of this magnitude are initiated by a reactivity increase of about one percent. ,
A.2 Evaluation of Energy Released during a Nuclear Runaway (1) Introduction one of the principal problems in evaluating the AGN-201 reactor is the extent of the energy generated in an accidental nuclear runaway. In this problem, the assumption is made that a step increase in reactivity is imposed upon the system and the only source of limiting the excursion is the negative temperature coefficient. A discussion of the problem is given the The Reactor Handbook - Volume I - Physics, and this general procedure is followed in this analysis.
r3
T -'
As a first approximation, cofisider that a 2% step increase above delayed critical is imposed upon the reactor. To bring the reactor to just critical again, there must be a temperature increase of
= 80*C au=ak/CT = 2.5 x 10-4 or an energy liberation of AE = (au) Mc AE = 80 x 12000 x 0.55 = 5.3 x 105 cal
= 2.20 Mjoule s A dynamic analysis indicates that approximately 2.2 Mjoules is actually released in such an accident.
. (2) Analysis of Accident Considering the time-dependent behavior of the neutron density, including one average group of delayed neutrons, one obtains
- for the time-dependent diffusion equations
0 6= Po - C.r8 n n + AC (1)
C = 0" L AC y *
(2)
P = b = E gnvc(Vol)
E pc(Vol)
(3)
Zgvcn
=
pc where n = neutron density (n/cm ) 3 Po = excess reactivity (dimensionless)
C T = temperature coefficient of reactivity ('C-3) 6 = tempdrature rise, ('C)
J = effective neutron lifetime (sec)
A-2 -
~
- = fraction of delayed neutrons (dimensionless)
I = reciprocal of the average mean lifetime of the 6 groups of delayed neutrons (sec'8)
C = average concentration of delayed neutron precursors If = macroscopic fission cross section (. cm-1) v = average therr al neutron velocity (cm/sec) c = energy per' fission (watt-sec/ fission = foules/ fission)
M = mass of core (gm) p = density (gm/cm 3) c = specific heat capacity (watt-sec/gm *C = joules /gm *C =
cal /gm *C)
Vol = core volume (cm')
E = energy (watt-see o.r joules)
P = power (watts)
The solution to the coupled nonlinear differential equations ~
(1), (2), and (3) yields the neutron density (and thus the power and energy), the temperature, and the delayed neutron precursor density as a function of time. Since only a first integral of the equaticns can be obtained analytically, a numerical finite difference method will be used in which equations (1), (2), and (3) become:
~
lPo - C Ti9\ S ng (t) = ni (3) + At j ni (t) 7 ni (t) + Ci(t)A -
6 C93 (t) = Ci (t) + at - ni (t) A Ci(t)
} -
Efvc Gi43 (t) = Gi (t) + At ni (t) s:v a Q.
A e
w.
a-
- These can be solved as functions of time once initial values for n, C, and are chosen. The initial values and other pertinent constants in the case of the AGN-201 operating at 5 watts with a 2%
step increase in reactivity inserted are:
.o=0 t
Go = 0 5 3 Co = 5.925 x 10 atoms /cm CT = 2.5 x 10~4/*C p = 0.0075 If = 0.074 cm"3 v, = 2.22 x 10 3cm/s'e c c = 76.6 x 10-33 cal /fis sion c = 32.1 x 10~33 watt-se c/ fission 3
no = (P/Vol) = 790 nuetrons/cm Egvc Po = 0.020 1 = 10-* sec A = 0.1 sec 3
pc = 2 watt-sec/cm *C = 0.478 cal /cm *C 3
3
- pc 6 = 2.64 x 10-3 cm - C/sec A t = 10 sec (3) Discussion of Results (a) Assumptions It will be recalled that in the above analysis the following assumptions were made:
- 1) At time equals zero, a 2% step increase in reactivity' was inserted with the reactor ht 5 watts.
A-4
4
- 2) At time zero, the energy in the core was negligible in comparision with the energy liberated during the accident. There was no heat removed from the core during the excursion. These are both very reasonable assumptions for the AGN-201.
(b) Results The numerical solutions (see Figures Al, A2, and A3) to equations (1) , (2), and (3) yield 75 mw for the peak power at t = 140 ms, a gtotal energy release of 2.4,1 Mjoules and a temperature rige of 100.7 C, as compared with the crude preliminary values of 80 C and 2.2 Mjoules arrived at in Section 1.
S A-5
TIC'2E J A-1: POWER vs 71P.I .
II+3
!. , ( N. '
a / \
J /
I / i 1E+7; '
s i '
~ \ .
1 i
is+6j \
=
- s
.i N
,1 W II+$. I
- /
/
=.
e 9
1E+4. /
I
- ,/
/
~
~
/
- 1I+3,
~u-1.
2 :
- r 3o e 6
2 53 190 1% K4 ue ?p II*E I.williseconis)
O .
A-6
IIC'JRE n-2: i.NERC's vs 11nt II+7
- i. I a
1 I
LE+i, 7 l 2
i 1
j /
?
?
1E+ 5.i 3 / ..
./ 4
. o
/
2
/
1E+ 4. / .
3
/
~
r
^1E+? '
s :
3 .
'7 vie *?. ,
's .
C 41E+1 ~
J 5?
- W 152 200 25a sea IIME (-ilIisecon.is)
O 4
A-7
HC:13E A-3: TEMPDATURE vs TfME 113 i
i IGG, e i
l [ !
ssJ l
es.!
79, , .
6 3.' '
l sa)' ,I i
t A
f V '
i II: ;
f 23. '
i- ,
I 10.
f+
e g --
_sl.
g 53 129 150 /.GG E50 30" TIME (*illiseco"40 d
O A-8
APPENDIX B
~
The following is a list of all earthquakes recorded from 1970 occuring within a radius of 100 miles from Albuquerque.
Description of columns: l idn - identification number for earthquakes date - date of earthquake (yr/mo/ day) time - time of earthquake (hr/ min /sec. 1/10 sec) lat - latitude of epicenter (degrees /sec/ 1/10 sec) long - longitude of epicenter (degrees /sec/ 1/10 sec) depth - calculated depth (km) mag - calculated local magnitude All negative numbers indicate that the recorded earthquake was insufficient in strength to accurately calculate either depth or magnitude using the computer codes at LASL.
'i .
i B-1
e .
i e 14e date time tot long depth' meg geet as ada date stee tot long depth' meg quel ne 1 73 9 18 00:39:33.30 34.4644 104.8867 4.30 8.9 $2 74 11 7 43s07:34.00 35.7594 108.4804 -9.98 1.1 8 73 9 19 13s89880.50 37.8500 184.3888 -0.98 8.8 3.0 53 74 11 ts 43135838.te 33.7854 104.9999 -5.Ge 3.9 3 73 9 19 81819:40.04 37.8000 104.8004 -0.90 3.4 $4 74 12 28 23:24est.50 35.3847 107.3687 -9.94 2.8 4 73 9 88 83:30835.80 34.5000 107.0000 -9.98 85 74 12 29 eletts54.44 35.3687 107.1968 -0.94 1.7 3 73 9 83 43s58154.94 27.1984 144.8004 -0.00 3.5 68 74 18 29 21:47s11.04 35.4887 147.4500 -0.00 1.3 4 73 le 13 43eS8:08.74 35.5478 148.2845 -0.99 1.5 67 74 12 30 18:11:28.14 35.0187 104.7000 -9.99 1.5 7 73 11 14 67154880.04 34.950e 107.0000 -9.98 8.4 se 75 1 3 las33st3.ee 35.2488 105.8810 -0.94 1.7 0 73 it R$ 18:45sSt.Se 33.5540 105.0810 80.00 1.7 E9 75 1 14 18:57e it.50 38.4333 107.3887 -0.94 .8 9 73 11 SS 18:58e01 30 35.5848 145.053e 88.44 1.7 7e 75 2 8 tes30ers.Se 38.144e 1e3.834e -e.De 8.7 te 73 18 84 88 34s13.34 35.5800 107.3810 -0.9e 3.9 73 75 2 3 08:23:37.98 34.5500 104.8887 -9.94 1.7 11 13 18 84 15eets18.50 35.4880 148.1838 30.00 8.3 72 75 2 9 09:18:35.70 34.870s 304.1970 38.00 2.0 18 74 1 4 83:49831.8e 35.0004 844.9000 -0.00 1.7 73 75 2 to 08:30145.78 30.8880 104.8454 38.00 1.3 13 74 1 17 83:04180.80 34.1150 148.1050 11.00 8.3 74 75 2 24 e4:e3s ts.28 34.434e 307.897e -s.co 3.7 14 74 1 17 83 00e84 34 34 1490 104.1000 -9.90 1.3 75 75 2 24 04:17132.48 34.4080 107.8410 -9.94 1.3 10 74 3 4 68855 s41 00 30.1500 108.8333 -0.Se 1.7 78 75 3 4 87818:52.7e 34.5494 107.0018 -0.90 1.3 18 74 3 7 13:58:14.80 38.0984 147.1480 -9.90 1.3 77 75 3 5 03:40164.50 34.5450 804.9970 -3.De 8.7 17 74 3 8 68s44s10.04 35 2887 107.7333 -0.00 1.1 78 75 3 8 87:58:55.9e 34.5550 147.0194 -9.94 8.5 38 74 3 13 10:15:08.30 34.3568 108.7404 -0.Se 8.0 79 75 3 7 03:38:33.00 34.8334 107.0343 -0.90 3.8 19 74 3 14 13 50839.00 35.4380 107.0850 38.00 1.1 se 75 3 7 07811:58.00 34.5130 3 07.18 04 -0.Se 1.8 Se 74 3 83 10:44818.00 38.9438 144.3900 38.00 8.4 81 75 3 7 16:35 34.00 34.4320 107.8578 -0.9e t.$
81 74 3 88 81055s48.00 35 8147 107.5500 -0.94 1.8 82 75 3 7 17:36108.1e 34.5844 108.9984 -0.90 3.4 83 74 3 80 88st4e30.40 35.8187 107.5500 -9.9e 8.1 33 75 3 7 18833:33.90 34.5110 807.0340 -8.90 2.0 83 74 3 38 88sS4e40.40 39.8887 107.880s -0.94 8.0 34 75 3 13 Itsetses.30 38.5300 107.0280 28.00 1.7 84 74 4 8 tise$e53 40 34.1380 108.8100 13.00 1.8 85 75 4 8 15113107.5e 38.1150 108.849e 83.00 1.5 SS 74 4 8 81848811 80 35.7140 107.1310 85.04 1.3 85 75 5 9 15:44e27.9e 36.2140 108.5850 -0.90 .3 38 14 4 0 14:13853.00 35.4844 148.7900 -0.00 1.3 87 15 5 18 at 30sts.94 36.4450 105.419e -9.96 2.0 37 74 4 18 19814s40.80 34.4880 148.7470 -9.90 t.8 88 75 5 16 07:26:22.50 35.8140 104.780s -0.90 2.4 80 74 4 80 80s43:01.30 35.9814 108.148e 0.0e 8.e 89 75 5 21 e4:44:50.00 34.7460 108.8420 -9.94 2.4 89 74 4 89 83e84 41.Se 37.4574 108.9756 -0.04 8.4 90 75 5 28 09821:38.84 35.7487 108.5333 -0.90 .7 ca 38 74 4 34 88147ste.70 38.7500 105.7833 -0.80 1.3 et 75 & at 05:4t:35.20 35.8744 303.6700 -0.90 2.5 ja 31 74 4 30 16:44:47.44 38.7006 148.9000 -9.98 1.5 92 75 8 25 07803843.40 34.9504 145.450s -9.94 3.4 38 14 4 30 14:10:35.50 34 4304 107.2000 -0.00 1.7 93 75 5 27 ele 39:24.7e 34.3470 106.854e 39.80 2.2 33 74 5 4 08s88150.00 34.8833 107.8867 -0.90 1.3 94 75 6 27 14:31 3s.1e 34.97se 305.e000 -9.90 1.8 34 14 8 4 8es 38 0 45.50 38.8500 100.9833 -0.99 8.8 95 75 8 28 07:24:33.24 34.292e 106.6214 -9.90 2.4 36 74 S 85 88 49 10.10 35.7800 108.4187 -0.90 1.3 94 15 7 2 02:34:22.80 34.3487 108.8867 -0.94 1.5 34 74 8 8 18:18:08.94 38.8487 tes.8847 -0.90 1.7 97 15 7 15 154 28:54.48 34.8187 1e8.1333 -8.94 1.1 37 74 4 Se 17:3t e te.94 38.1187 105.8333 -0.90 1.6 98 15 7 28 07 s 4 4 e 37.80 34.5887 148.7333 -9.90 2.1 38 14 8 88 e5153:48.83 35.0033 300.7e00 -0.30 8.4 99 75 8 19 23166128.00 36.3934 104.5980 -0.90 1.5 30 14 7 11 11eB8857.00 35.8930 1e7.9300 -9.9e 8.5 tee 15 8 25 12:21:14.40 35.7ste 105.7750 17.44 .s de 14 3 14 etsteede.Se 37.8740 107.87e6 9.90 g7 act 75 9 29 18:01150.00 38.120s 100,1404 8.44 .3 41 74 S 18 10:47s48.30 37.1140 147.0474 -0.94 1.7 102 75 9 4 ese25124.te 35.2tge 108.4553 -0.9e 1.5 48 74 0 SS 07:33s01.Ge 34.5450 105.0000 -9.94 8.7 te3 75 9 8 43e48e54.4e 38.1120 108.8139 17.4e 3.3 43 74 8 88 88s81:34.44 25.8500 10s.0000 -0.00 .1 104 75 9 7 40124e07.80 38.1730 1e8.3930 33.00 g,3 44 74 3 34 88s57s38.44 34.3333 107.3387 -9.90 3.3 185 75 9 7 13:43 27.94 38.1750 108.1940 11.00 1.4 45 74 9 11 10:58 04.40 28.8333 tes.9887 -9.90 1.0 tes 15 9 to stests40.at 28,117e 1e5.e293 -9.Se 2.0 44 74 8 13 81:13:19.44 38.4410 144.9804 -0.90 1.8 107 75 9 15 e7stes54.ae 38.aste 1et.1338 13.00 3.1 47 74 0 80 13:13:40.10 33.3470 103.4534 -9.90 3.1 180 75 9 17 04107133.90 38.eSte 104.8550 -0.90 1.8 48 74 to 11 itsefe87.Be 38.0140 100.0470 -0.ge 3.8 100 75 9 18 41:48:17.50 35.9800 lot.7700 33.00 1.s 40 74 le 15 09e30se8.74 33.0333 108.8333 -e.94 3.3 110 75 9 35 03e30se4.se 34.3300 308.834e 15.00 1.8 80 74 le 15 19 8 98188.40 33.8333 138.5e33 -e.Se 3.3 111 15 8 25 15stesse.88 38.st3e 10s.735e 38.00 .5 8174 le 18 14:47157.70 33.0333 tes.ts33 -e.Se 3.s 112 75 9 37 lase 7 sat.40 3e.000s tes.e487 -s.se .
88 741e 18 testes 34.e4 33.0034 108.7340 g.90 1.8 113 15 9 29 ttse914s.4e 35.04te tet.7s7e 13.00 3.8 83 74 to 18 18:47:30.30 38.asse 1e7.e333 -3.ge 8.0 114 15 5 30 list 4s20.Se 35.0000 108.838e 15.ee .5 5414 to 18 44s30157.3e 35.0884 108.7384 -0.ge 8.3 185 15 9 29 11:17 07.40 38.9850 148.8200 18.06 1.8 06 74 11 1 89:30st4.80 33.9307 see.850s -s.ge 3.1 118 15 e 80 13:53:44.34 35.950s tet.08te -0.94 1.1 84 74 11 1 60844810.80 33.9107 100.880s -e.90 1.5 117 75 8 as 13:17:18.3e 35.9740 108.8454 18.00 8.e .
87 14 11 1 14:43:38.e4 33.9137 104.g000 -3.99 1.7 110 15 9 29 14e19:48.8e 35.0000 148,8830 13.00 .8 SS 7411 1 18848e50.70 33.0147 348.0500 -g.00 8.8 119 75 e 58 14:47:08.34 35.0010 188.sete 85.00 .5 80 74 11 1 11888:58.80 33.9101 144.0500 -0.94 1.8 12e 75 0 88 1718ests.se 33.970s 100.7570 18.00 .5 de 7411 1 10e11:48.30 33.9107 148.8800 -9.94 18 321 75 le 3 45e43e41.Be 34.1830 106.9058 E.00 1.5 81 74 11 S 19833118.04 30 1800 144.9000 -e.se 1.3 tat 75 te le 07:18:38.50 34.8333 107.5333 -0.90 1.5
o 14n date Llee tot long depth' seg goet ne tan date 4 tee tet long depth' esg quet ne 133 75 to 18 18:18s58.70 34.3900 104.3480 -9.94 2.1 194 76 7 8 e4 s 45s49.83 35.4978 104.0458 -9.94 1.5 i 124 75 to 17 15 45 set.50 35.3760 10s.2000 20.00 2.4 135 78 7 8 tas40s45.40 38.este te4.8850 -0.94 8.0 125 75 le 31 04s08s15.9e 34.0550 te6.8600 29.00 1.4 188 78 7 7 88 37s08.07 35.3594 107.9040 -9.94 1.3 IIS 75 11 5 02 s 44 12.20 34.8544 196.3333 -9.Se 1.7 187 78 7 18 a n s e4 s te.80 35. Site 107.0000 -9.De .8 127 75 11 4 43s30s22.se 34.5eet 185.8033 -0.93 .8 ISO 78 7 31 at:SisSS.Se 35.4840 te8.487e -9.De 1.7 128 75 11 8 13 45s24.8e 38.530s 145.1840 -9.94 1.8 139 74 8 3 00stes44.58 34.8580 808.8480 -9.9e 1.1 l tto 75 la 3 to 12s2e.4e sa.9ese tes.7ees -9.se 3.8 toe is e e lase 8 s 47.03 38.74ee lee.st7e -0.ee .7
, 13e 75 tt 3 13:4t:31.14 35.7884 105.1688 14.30 1.1 198 78 8 10 00sess38.54 34.1488 147.3134 -0.De 1.0
! 138 78 1 1 23s44sts.08 38.0350 106.3200 -9.93 .2 192 78 8 13 e7s38:11.00 38.4558 107.3450 -0.94 .7 j 132 73 1 5 e6:23s33.70 35.8930 197.9770 -9.90 4.0 193 78 9 30 33:47s38.88 35.1944 104.0510 -0.94 8.8 133 78 1 8 08844s99.3e 35.8809 108.3004 -9.90 1.6 194 75 0 t its38s34.30 35.8840 107.4140 -0.94 .5 1 134 78 s 2 atit8see.se 34.<sse 104.78ee -9.9e 1.8 195 is .9 8 e5:49sts.33 35.e34e toe.es4e -0.9e s.e 335 78 1 33 to 43:21.4e 35.8934 103.4018 -9.90 1.1 196 78 9 18 18:59188.80 35.3830 107.8500 -0.94 1.8 138 78 1 12 22s50ste.tr 35.204e 104.210e -9.90 .7 197 78 9 13 08 44 8 09.30 35.3848 107.3446 -9.De .7 137 78 s 14 37 sets 31.2e 34.205e 194.8800 -0.9e 1.0 198 78 9 15 04 33s47.00 35.454e 107.4830 -0.94 .5 138 78 1 18 22s97st?.32 35.583e 107.0600 -9.90 2.3 199 78 8 19 19:34 s 48.31 34.0910 108.8194 -0.De 1.7 139 76 1 19 13 34s35.98 35.5334 100.0720 -9.94 1.3 200 78 10 2 40 s t 3 s 31.43 35.9578 108.8348 -0.De .7 343 78 1 at 13s49 28.02 38.4940 198.es5e -9.90 1.9 201 78 to 4 ess30s57.7e 35.3280 807.3260 -0.De .8 141 78 1 32 28st2s48.54 36.35s4 806.5308 -9.98 .3 202 78 10 8 11:33844.00 38.5530 108.5794 -0.94 .8 142 78 1 24 23sses27.20 35.3854 le7.2700 -9.94 .3 203 78 10 8 11:40s15.34 38.8350 108.8820 -0.90 .5 l 143 78 1 35 07:28:14.30 35.422v 807.2979 -9.98 .3 284 78 to 8 18s47s44.52 38.7100 108.5894 -0.04 1.1 144 78 1 25 19851812.10 35.3870 107.3218 -9.90 8.0 285 75 to 8 18s44s33.98 38.7314 148.7070 -0.98 .8 145 78 2 19 83:47:42.43 35.2188 147.7850 -9.9e .1 286 76 le 8 15s44s50.80 35.4380 168.8870 -0.58 3.7 i 848 76 3 7 07s40s57.22 35.2004 196.1300 -9.90 .7 297 78 to 8 19:20s19.98 38.7134 106.8930 -0.90 .8 l 147 75 3 7 12:18:25.44 35.6958 147.9798 -9.90 2.3 248 75 le 8 19:29:57.78 38.8334 168.8730 -9.94 1.5 148 78 3 16 13:30se9.30 37.0554 195.5320 -9.9e 1.1 200 78 le 8 19:33840.88 38.5000 108.8450 25.54 1.3 149 76 3 21 20:22:58.80 36.9470 146.2448 -9.90 1.0 217 78 to S 20 18813.17 38.1510 te6.0344 -0.94 .7 15e 78 4 1 14:40s29.84 34.0850 106.4920 -9.94 1.5 211 75 le B 20:42:34.31 38.8700 108.5870 -9.90 .8 151 78 4 1 14:48s59.43 34.146e 106.e940 -9.90 2.4 282 78 to 3 21sess34.4e 38.8380 108.5830 -9.90 .8
' CD 152 76 4 1 14s51st?.94 34.0714 106.t198 -9.90 1.3 213 75 18 9 44:50:38.99 38.7554 108.7240 -0.94 .8 8
'# 853 78 4 3 33s30s37.75 34.0969 106.0250 -0.90 1.0 284 78 10 9 4 t:14:41.39 38.8000 108.8410 -9.94 .3 154 78 4 3 e5:55:58.88 35.2354 106.1140 -9.98 .7 215 78 le 9 93:47847.88 38.9458 104.7840 -9.90 1.0
! 155 78 4 8 18:09:02.28 34.1180 104.4940 -9.90 2.7 + als 75 to 12 14:57s37.57 35.3534 107.03te -0.94 1.3 158 78 4 to 22s39s33.48 38.2780 106.1800 -9.94 t.8 287 78 10 18 05:42s34.31 37.0340 148.8400 -9.90 1.8 157 76 4 11 87 4 4 s e2.2 4 38.2450 108.22t e -0.94 1.7 215 78 to 21 03:50 s 24.57 34.8880 145.8384 -9.De 1.5 158 76 4 11 47s45s31.43 36.2794 tes.20Ee -9.90 1.3 219 78 to 28 49:43s29.41 35.9574 107.1880 -9.94 1.7
! 159 78 4 17 42s4es33.45 38.1050 108.9270 -9.90 .5 22e 18 to 22 tes34sts.51 25.3040 100.0014 -0.94 .8 184 78 4 17 48848821.74 38.3734 188.3960 -9.9e .7 221 78 le 34 078 tg8 88.e4 38.9904 188.4014 -0.De .5 181 78 4 18 43:48820.3 34.0498 106.1260 -9.94 1.9 223 75 le 27 19:50s53.98 35.3394 847.9806 -9.94 1.1 ISS 78 4 18 46820st2.82 34.4350 106.0898 -9.94 1.5 223 78 11 3 31645s08.De 35.4500 101.1810 -0.94 .O 883 75 4 18 15:54s48.07 34.e769 106.9530 -9.90 1.9 224 78 11 8 37s44s58.Se 35.4540 107.3524 -9.94 1.1 184 78 4 19 05se3:41.12 34.1539 105.8738 -9.90 1.5 225 78 11 0 13:34s49.Se 33.333e 107.1430 -9.Se .g 145 78 4 19 12:35st2.38 34.1474 106.9288 -0.90 1.8 228 78 11 it testeste.e5 35. Stet 306.2449 -0.90 1.0 188 70 4 24 68814:28.14 35.7170 105.7790 -0.De .3 227 18 11 10 .48s54se4.88 38.4806 108.0454 -0.00 1.3 187 78 4 24 08:24 42.00 35.7866 105.7510 -9.94 1.4 228 78 11 20 41800:39 53 38.1848 147.3830 -0.94 1.1 180 18 4 29 23 s e3 s t 2.45 34.8 480 125.3830 -0.90 1.4 229 78 11 27 19:43:38.08 35.3990 147.8880 -9.90 .7 169 78 5 2 ess32:38.81 38.2884 108.2780 -e.00 9.7 234 78 11 27 tts57s38.20 35.3054 107.0704 -9.90 .8 170 74 5 9 03:54ses.88 34.3876 104.930s -0.94 3.3 231 76 11 27 12s3es33.34 35.3333 107.8847 -9.94 .5 171 70 5 le 07:35s37.08 35.5084 107.2454 -9.9e .7 232 70 Il 27 18:34:10.99 35.3880 107.0380 -0.90 1.7 172 78 5 41 45 s t 3 s 41.51 35. 45 20 10 4.08 40 -9.90 1.3 233 78 18 to 1484aste.07 3e 3834 308.84 8 -0.04 1.3 173 18 5 38 30s50 30.30 38.3t20 105.921e -9.90 .4 234 78 at 17 19841:50.98 35.9908 108.1830 -0.90 1.4 174 78 5 22 14:04s59.50 38.3330 195.9240 -9.99 .9 235 78 la 33 ets34s50.40 34.1700 105.8440 -0.98 3.4 175 78 5 28 47stes39.55 34.7994 105.2940 -0.9e .3 230 70 la 34 1383333.13 3g.8589 tes.Sete -0.04 1.3 178 78 8 1 tes40ste.94 33.3e46 108.2006 -0.94 3.4 237 78 12 as 48s40:07.43 34.3g00 138,384g -0.9e 3,8 377 78 0 0 43:57st?.49 30.1570 198.2960 -0.94 .7 238 70 12 30 13:37:48.08 34.9180 105.7954 -0.00 .8 178 74 8 8 40:24:40.14 34.0350 148.9848 -9.90 1.4 239 78 13 31 07s53:46.52 37.7154 186.6428 -9.94 8.3 179 78 8 9 17s37:46.83 34.4958 108.9740 -0.90 2.2 240 78 12 31 47s53:58.70 38.573e 108.873e -9.94 3.3 184 78 0 84 15:27:32.29 35.5954 183.7398 -0.90 3.0 341 77 1 3 01:08838.54 34.4870 145.883e -9.00 1.5 181 78 8 af tas55s39.30 30.4350 108.3038 -9.90 3.e 248 77 1 4 18:31:48.8e 33.8319 3e8.3390 -0.9e 8.7 188 78 8 30 Sts11:35.58 34.1454 108.3730 -0.94 1.5 843 77 1 4 83s41:59.50 34.1170 168.1380 -9.go 2.7 183 70 7 5 13:39:19.43 38.1384 106.2600 -3.90 8.3 344 77 1 5 03s19815.80 35.6889 106.5820 -0.99 .5
l s s
j e I#"
- I" "I ada date Lise tot teng depth nog p al na 3eg ?? 7 3 61:34848.50 30.2110 107.0934 -0.90 1.3 4 245 77 1 5 testeset.4e 34.1338 los.4870 -9.94 2.4 3e7 77 7 30 30 09s45.5e 35.4700 107.3570 -0.90 s.1 l
ses 77 1 e 13 sets 5s.5e 3s.egne les.e79e -0.9e s.3 us n 7 na 19s5ss35.se ss.Stee te?.Sese -e.De s.8 247 77 8 9 1Bs et s5 4.54 34.0954 105.8340 -9.00 1.5 1.7 Je9 77 7 28 07:44s30.30 35.7040 144.8710 -9.94 -0.9 248 77 1 9 13s05:15.10 34.0244 105.9810 -9.04 1.5 3te 77 7 29 ges42ses.90 35.2464 104.3480 -0.90 .8 249 77 1 11 44s59:44.24 34.0940 tes.eSte -9.90 .E 3t1 77 8 5 16:08:28.24 35.3354 107.3410 -0.90 .7 250 77 1 20 23:26:45.ge 36.3440 108.276e -9.98 312 77 8 11 e4:24:53.34 35.8880 148.1848 -S.90 .7 253 ?? 1 21 16s34:38.10 34. leet 147.0198 -0.90 1.8 313 77 3 13 33:00:02.6e 35.4080 100.4839 -0.9e 9.0 352 77 1 22 87st38te se 34.3098 145.8460 -9.94 t.1 314 77 8 13 87:59:18.30 -9.94 1.8 253 77 1 27 1e:43:11.64 35.8438 140.0460 -0.00 1.1 ggg 79 g g4 g4,4g,33,g, 34.5810 34,gggg 140.88,70 ggy,94 g .g,gg g,g 254 77 2 1 12:44s37.04 36.6830 106.670s -9.94 .a 388 ?? 3 19 09:33s43.4e 34.0530 107.8358 -0.94 3.8 255 77 2 3 44:46s58.94 35.7600 147.553e -9.90 .57 387 77 3 29 13s53:09.40 34.5314 144.7100 -0.90 14 25s 77 2 17 13sess40.50 38.6874 548.8304 -0.90 333 77 e at 05:43 s25.70 35.8444 106.478e -0.94 .7 257 77 2 as 10s55s35.se 38.7508 144.3458 -9.94 e.0 .8 319 77 8 28 15s10:54.28 35. Site 107.3400 -9.94 3.8 25e 77 2 26 84s3tsts.te 35.3720 107.3600 -9.90 320 77 8 28 21:44:33.50 35.0129 148.127e -0.90 0.0 259 77 2 26 17:40st?.24 35.4240 107.3304 -9.90 .5 328 77 8 37 48841s88.40 34.1884 108.8138 -0.94 15 280 77 2 28 18:12828.68 35.4220 107.3220 -9.90 .5 322 77 8 29 47813830.30 35.5989 107.074e -0.94 1.0 261 77 3 2 00:54s18.7e 36. esse 105.1834 -9.98 1.8 .3 323 77 8 29 07:37:19.40 35.8590 107.3010 -0.94 0.0 262 77 3 3 13:35:45.80 35.9954 148.1410 -9.9e 4.3 324 77 8 29 08 03:49.24 35.4500 107.8447 -9.94 0.0 253 77 3 5 03:44:56.00 35.7200 107.730s -9.99 .8 325 77 8 2e 08:38838.50 35.58te 107 1e94 -0.90 0.0 264 77 3 5 05:28:59.30 35.7360 147.9454 -9.99 2.2 328 77 8 29 32s17s00.00 34.323e 104.0030 -0.90 1.e 2ss ?? 3 9 15s35s33.e4 35.8440 108.162e -9.98 327 77 9 1 83848 s 48.5e 35.5330 te7.Gele -9.94 .8 2gg 77 3 18 14:04s41.34 36.97te le6.9760 -9.99 2.2 328 77 9 2 11:29s23.00 36.5404 147.007e -S.Se 0.4 267 77 3 30 14:55:01.90 35.4860 147.3270 -0.00 .4 320 77 8 9 17:58:43.34 35.1868 107.4529 -9.90 1.3 258 77 4 3 eta 23s44.90 35.4404 107.3804 -9.90 .5 334 77 9 17 ets 04 s27.te 25.8220 148.8914 =9.94 -0.9 l 259 77 4 3 01:24:38.34 35.4330 107.3148 -9.9e .5 331 77 9 19 23:58:35.04 35.7784 188.1520 -9.90 .3 274 77 4 3 ets30:58.00 35.4324 807.3480 -0.94 .5 332 77 9 29 ets22s23.5e 35.8044 148.8978 -9.90 1.0
! 271 M 4 3 19:2549.48 56.4G00 106.2400 -9.90 2.4 333 77 le 2 14 s 33:35.2e 35.784e 106.9458 -9.De .7 272 77 4 7 13:13:03.54 35.4E2e 147.2180 -9.90 .7 334 77 to 4 05:40857.84 35.7800 108.9790 -0.90 -9.9 273 M 4 9 18:08 02.44 35.8834 105.4198 -9.94 1.3 335 77 to 4 46100s00.56 35.7370 148.8500 -9.94 -9.9
, 274 M 4 tt 18s45s35.94 35.4460 106.9624 -9.98 .8 338 77 le 4 34857s42.30 36.2190 146.7674 -9.94 .8 a 275 77 4 14 15:24 s 25.30 34.7330 tres.7680 -0.9e .5 337 77 to 8 04:20:52.40 34.7348 104.4264 -S.9e .7 l 275 77 4 17 48s2150.14 35.3420 107.38B4 -9.98 1.8 338 77 le 12 31:00:11.50 34.3834 106.7310 -0.90 10 277 M 4 17 es s 40 s 53.54 34.1414 184.7750 -9.90 .8 339 M te 13 05:58 44.74 34.1070 106.3100 -9.9e .8 278 77 4 18 03:12:55.50 36.5494 146.6328 -9.90 .8 340 77 to 13 1983Ss17.70 36.9500 106.0000 -0.90 1.0 279 77 4 18 e4:27:40.24 34.22Ee 186.0240 -9.98 1.1 341 77 18 25 00 sate 43.74 37.073e 108.1884 -0.90 .3 200 M 4 24 13:37:33.40 38.3tse 105.8170 -9.9e .3 342 77 to SS 13seest4.24 34.335e 148.9390 33.34 1.1 283 77 4 25 09:28:27.80 35.4000 107.3444 -3.94 0.0 343 77 11 4 13s31s30.40 38.7334 105.4000 10.20 .5 282 U 4 26 tts35se4.58 36.eS9e 106.1590 -0.98 0.0 344 77 11 7 03:43s55.10 34.2740 110.3914 asses 3.1 283 77 4 24 11:59847.90 36.1110 146.2410 -9.99 .5 345 77 18 11 11:38:54.94 36.4800 107.1044 33.9e .3 284 77 4 to 12:0143.38 35.0998 10 .3 348 77 11 14 47:28 27.00 32.8396 104.5130 assat 3.1 285 77 4 28 12s41884.34 36.1644 6.23se 1.6.2720 -9.540.0
-0.90 347 77 11 18 00:59 00.24 35.3294 1e7.4334 13.34 4.0 288 77 4 29 05:18:34.30 36.3438 107.3270 -0.99 .5 348 77 11 18 09:20s21.29 35.6164 107.2170 14.70 e.e 287 77 5 to 06:55:38.99 35.3589 147.6400 -9.90 .5 34g 77 11 17 13 02 29.70 35.5894 105.9968 36.9e .2 288 77 5 13 03s19:4 35 1.0 2:e M 51 us40s.6.345.it 3. 5500tes.Mie
. i000 290 77 5 22 15 51832.10 35.4594 tes.ette -9.94 10G.0954 -0.90t..
-9.9.
1.4 35,4 31 n 77 12, 3 2,
. ,12, s,, ,t e s,ge,?,3,; 9,4 35 3 : ,8
,11. 5,5,0 106. ,19,8,,4
, e:e.
8,3,;'7
, 0, 353 M la 3 3870 13*le 1 21M E 23 0$s42see.98 35.4890 148.2530 -0.90 e.4 353 77 18 3 48840s45.1035.3544107l5seea3.3e 20 31:33.3e 35.03se les lg 292 M 5 23 18 05s47.40 34.4450 tes.2498 -0.00 1.4 354 77 18 to oe s t 3 s se.80 38.88M 3 08.7554 48.90 .e 293 77 5 20 40:43:51.24 30.0933 108.8833 -9.94 .0 385 77 tt to eas50s57.34 35.7304 108.8304 -0.00 .8 294 M 5 27 48819:05.00 38.4790 144.5528 -9.94 .8 358 77 12 32 10:29:11.50 38.0440 148.8440 -0.00 0.0 205 M S II 23:14:15.20 35.4e80 147.13t0 -0.90 .7 357 77 18 13 .3 208 M 5 29 e5stes42.50 35.5334 147.0518 -e.90 I.3 3sg yy gg g4 et e 48 s 58.30 gg,4g3g*gg 35.gne ggg*ggg 3g*gggg 103.3300, 34.94 g gg .'g 207 77 5 14 47:01:15.9e 34.1750 807.3230 -0.94 1.1 jgg yy gg 3, g3,ggggg.44 35*ette le7 Se7e 15'*5e *s 200 M e 3 18 41825.50 M.7Ett 106.28t4 -0.99 1.2 309 77 la 21 test $s34.00 35.4330 te7I3300 13.30 .3 2GG 77 8 7 ets58st2.16 35.7234 les.6210 -9.9e 1.0 301 M 38 34 13 30e 77 E 11 04:59 54.3e 34.2'3e 106.4546 -3.94 .1 3gg 99 gg gg 19:30:33'.to gggggggg se 35 4819 108 36.3100 108 Sept 140058.De 13 4e 1.0
, 301 77 8 43 10:37st?.54 14.0550 188.1160 -9.90 .3 303 70 1 3 ess30s54.te 36.4050 107.0464 0.84 .1 l
308 77 8 16 09:28:22.44 34.5968 184.837e 9.94 1.1 344 78 1 14 03:49:59.99 35.1980 104.8490 50.00 1.8
!!!!!!0!!!U!!!!!!!!!!'i!!!!!!!!!!!!!!!I!! SU U ! U U 53 U:n U :U U IU : U ::n ::
e ida date Lise tat tong depth eng quel na Ida debe tise tot long depth' meg quel me 367 78 1 3e eas53 set.50 35.90ee 104.g32s 3.7e .5 488 78 5 7 14 30 s s8.74 34.3510 168.8)e4 13.24 .4 30s 78 2 1 45 47s19.18 35.5720 804 5120 31.80 .8 429 78 5 9 0e 41s04.10 35.4150 108.4304 54.se t.2 389 78 2 13 09s48ste.43 36.807e 106.845e 4.30 .e 430 78 5 28 05:31841.90 34.9434 106.1500 44.10 -9.8 370 78 2 13 38:57:39.40 35.7690 107.1450 20.10 1.7 .7 431 78 5 as else4ses.34 34.3544 144.4e70 12.04 .8 371 ?g 3 14 esselst).te 15.4248 107.3180 34.30 138 St.se 1.0 373 78 3 14 16 49805.70 36.2364 tes. gees 13.at 1.8 433 78 7e 5e 28 48s57s34.0034.1764 1 45s93s32.20 34.3440107.0998 364.8636 44.50 1.1 373 78 2 15 07:38s50.60 38.3)ee 106.780s -0.90 0.0 434 78 8 8 88834:57.30 34.9449 107.830e 19.74 1.1 i 374 78 4 la 13826:16.80 36.6964 109.1814 31.54 e.0 1.4 435 78 8 4 20:43s08.4e 35.4644 149.44e4 48.84 1.5 375 18 2 23 tis 30s41.te 36.68E8 106.7398 18.28 434 78 8 8 10s00:48.00 38.8300 164.981e 28.76 3.3 ;
373 78 3 33 tas43s45.te 38.320e 105.8170 32.70 .3 437 78 8 88 ess4ss53.14 38.3580 104.0474 55.54 1.1 377 78 2 26 18s27s49.98 18.2900 105.8474 9.70 .2 438 78 4 33 13:32s41.50 35.3368 194.3414 86.44 .5 378 78 3 te les44s24.40 35.4296 107.3300 -9.00 .3 .3 438 78 8 as 04s33 set.04 35.3344 103.5004 -0.94 1.5 379 78 8 24 16:36:05.90 35.397e 107.3184 4.9e 444 78 8 38 44s44sse.84 36.4184 194.4464 24.58 .0 ,
330 73 3 20 01:15:47.80 36.5330 108.0980 8.70 e.9 441 78 4 29 essat s53.50 38.814e 104.851e 48.74 .3 '
388 78 3 I tes44s22.00 34.4970 108.7450 18.00 .7 448 78 4 20 88s t3s 41.54 34.5488 144 1980 58.De 1.3
! 382 7s 3 8 18s48s86.84 35.483e 107.4424 18.80 0.0 .3 443 78 4 34 09:42s40.te 35.1516 197.9484 13.94 1.1 383 73 3 3 46s30se6.20 35.4240 107.3304 -9.90 .7 444 78 7 8 14:37:43.7e 36.7104 104.5254 18.34 .8 445 78 7 3 15:13s47.64 35.5814 107.2500 26.88 4
.5 l 3s4 78 3 5 eas50s32.00 36.623e 105.4764 14.50 448 78 7 9 13830 18.44 34.8583 166.este 14.e4 1.3 385 78 3 8 e7:08s18.6e 34.2354 106.770s 55.8e .8 447 78 7 17 17:05s11.44 35.4380 166.t710 5.te 1.4 344 78 3 8 13:28823.70 34.4830 106.923e assas -9.9 448 78 7 St 46804:37.74 34.8748 195.2450 50.34 4.8 387 78 3 6 12:28 s24.00 35.670s 10 4.750s -0.9e -9.9 449 78 7 24 ess46s44.50 34.8550 107 1194 44.94 10 388 73 3 7 00s42:30.40 34.lete 804.7834 sanss 1.6 4.50 1.7 454 78 7 37 86s53s26.le 35.3968 147.644e 43.18 3.3 333 73 3 8 178e7:30.2e 36.4810 106.816e 7.90 .5 451 78 7 28 21sess56.se 35.9e5e tes.eese 44.80 1.1 39e 7s 1 12 00 34:11.40 36.0900 106.236e 452 78 3 5 23:08:44.00 35.453e 104.1784 7.20 1.6 371 78 3 12 02s20:43.00 36.1110 105.2074 10.94 .5 .5 451 78 8 15 e6:55see.Se 36.7054 108.5754 35.74 1.3 392 78 3 52 02:20s46.50 35.e36e 106.2648 88.10 454 78 8 34 22:58see.40 34.438e 1D4.6894 88888 393 78 3 12 e3seesse.1e 36.1914 108.2284 -9.94 .3 .8 394 78 3 12 86804:42.00 16.875s 106.2430 8.44 .8 455 78 8 31 94 stas 34.40 35.0848 148.5530 42.8e 456 78 9 3 15 59 14.18 34.547e 146 1689 44.7e
.5
.8 395 78 3 12 06:22:07.0e 36.1010 106.2280 8.30 CD .I 8
396 78 3 12 11:41:58.04 36.1950 146.2260 g.00 .3 457 78 9 5 tes33s22.20 3 4.5360 104.1700 41.20 1.4
'" 458 78 0 19 07:3348.70 ;;.2789 145.7970 26.60 1.1 397 78 3 12 13:19s58.99 36.1450 196.2394 8.70 .3 390 70 3 14 18 43:23.50 36.4230 145.2854 1.Ge 1.5 459 78 9 23 88 59:53.78 34.5640 105.9610 98.30 .8 399 78 3 17 43st4:37.4e 34.1488 te6.813e asssa 1.1 464 70 9 24 18:01847.30 35.7580 106.770s -9.98 .8 44e 78 3 17 11:41s40.50 35.4680 107.5490 11.10 .7 461 78 9 E4 18 39:49.40 35.811e 108.717e 0.00 .8 481 78 3 17 19:40828.30 35.1804 100.3480 49.10 .3 462 78 9 24 18:27158.2e 35.7594 104.7704 -9.98 .4 442 78 3 19 03 29835.00 34.7560 105.9750 assst 1.0 483 78 9 24 20:34s33.44 35.750s 144.7700 -9.94 .8 4e3 78 3 te 22:5te46.te 36.1500 105.643e 7.44 .5 464 78 8 24 20:38s48.40 35.7500 166.7744 -9.98 .8 444 78 3 22 e4:29 817.74 35.1830 1s5.6864 4 4.60 -9.9 445 70 9 24 20:47:33.14 35.89te 144.7214 11.00 .8 445 79 3 22 06:27:44.50 36.4204 106.5704 -9.90 -S.9 464 75 0 24 21410s51.44 35.702e 106.827e 3.20 .8 ese 78 3 30 13:41s41.80 35.3404 147.3300 11.30 -9.9 447 78 9 24 31:34s13.00 35.7584 tes.??te -9.90 .3 447 78 4 8 47s35s48.50 35.2380 te7.ette 19.30 1.1 488 78 9 24 21:43:15.70 35.750s 104.7704 -9.94 .8 408 78 4 9 22s34s42.80 35.3950 107.3000 7.54 .7 489 78 9 34 33 37135.44 35.7500 106.77e4 -9.94 .8 489 78 4 13 4G:07s44.00 34.2444 106.360s -0.C4 -1.3 47e 78 9 24 22:38:16.00 35.7850 164.6000 it.se .0 418 78 4 18 es s 38:14.10 34.4400 107.0880 14.20 1.1 471 70 9 24 23sl5 sat.de 35.8300 144.9844 -0.94 .8 .
481 79 4 18 ete47stG.39 36.4554 107.1344 11.20 .5 478 78 e 24 33 s 24 s et.Se 35.7500 166.7704 -0.90 .8 412 71 4 23 13:11s40.30 35.4924 146.9848 24.20 .5 471 78 9 84 33s28828.3e 35.7460 104.0450 10.10 .4 413 18 4 33 17s00:38.G0 35.869e 108.9834 9.te .5 474 78 9 25 00:31850.14 35.7310 108.7410 10.44 .8 414 18 4 23 17s41se7.99 35.418e 100.2188 5.54 .e 475 78 9 25 00s37s23.50 35.7930 104.7558 14.90 -1 7 415 78 4 23 17:45s34.20 35.4850 108.3440 4.te .4 474 78 9 38 ess40ste.30 35.0174 164.733e g.Se ..e 418 78 4 23 33 25:35.20 36.8648 106.9629 15.94 1.1 477 78 9 45 00:50s18.90 36.8430 104.7820 14.se .p 417 78 4 23 23:59:50.20 35.57e0 104.9830 10.00 .8 478 78 0 35 04:53818.34 35.747e 164.7514 9.04 .C 410 70 4 24 00:03:30.58 35.8500 104.9500 17.00 .4 474 78 9 25 01:13824.00 35.9580 tes.sete 19.30 .8 419 78 4 24 02:09s24.54 35.895e 106.9489 18.90 .8 490 78 9 SS et:45s37.30 35.7500 144.77ee -9.80 -e.9 42e 75 4 24 43:01:25.20 35.0924 106.9464 19.50 .8 481 70 9 36 els 47 sat.89 35.7500 146.770s -0.9e -9.9 423 78 4 27 10:45s20.19 34.0000 105.0000 -9.44 .5 482 78 8 35 81855s47.30 35.8880 tes.7330 at.go .8 423 78 4 27 31s41:20.78 35.1410 106.1874 96.50 -9.9 403 78 9 25 04:03 57.50 38.750s 100.7704 -0.00 8 423 70 4 30 80s32s44.te 38.6450 100.5304 7.50 7 484 70 0 35 03 07:44.88 35.1884 108.7330 11.8e .4 l 424 70 4 3e 04 34st3.50 34.5370 106.4979 2.te .5 485 78 8 25 03:11:40.18 35.0884 tes.7tes 13.80 .8 425 78 5 3 04:43:37.34 33.3958 106.8450 18.30 .3 488 78 8 45 04:12:07.00 35.1350 104.731e 11.30 .4 i 428 75 8 8 00stis44.te 35.503e 107.8380 11.50 1.4 487 70 9 35 00 stas 31.30 35.787e 103.7ege 13.00 .4 487 78 5 8 c1:14:38.80 35.4700 107.3e39 8.3e .5 488 78 8 88 castls47.44 35.814e 108.7084 14.40 -0.9 l
l
{
l I
?
ada date tsee tot long depth =eg qual ne ida date taee tat long depth seg quet as l 489 78 9 25 88:15 58.04 35.7484 198.7380 11.80 -9.9 550 78 9 20 00s5044.30 35.8178 194.8964 -9.90 .5 498 78 9 25 ete17:49.70 35.7310 148.7380 10.18 .3 551 70 9 29 418E8:35.80 35.3178 148.8844 -0.04 .3 491 79 9 25 02:19:15.80 35.7500 198.770s -9.90 .8 552 78 9 29 88828e19.88 35.2174 188.0886 -9.9e .5 402 78 9 25 02837:10.00 35.7390 108.8480 8.29 -1.7 553 7e 9 3e tes36sts.30 35.2004 104.8108 27.10 .8 493 78 9 35 92s27s53.20 35.9888 846.7900 15.10 -1.7 554 78 9 38 64:3980s.30 35.2170 144.8800 -8.99 .3 494 78 9 35 02:28 s t 4.20 35.76es 194.7398 8.98 .5 555 18 f 30 00eSte40.58 35.3174 194.8204 -9.94 .5 ,
485 78 9 E5 efe32148.le 35.7158 106.7240 11.70 0.0 555 78 9 3e 08:18:53.30 35.3104 100.0380 38.40 1.8 488 78 9 25 02:44848.te 35.7584 148.7748 -0.96 -1.7 557 78 9 30 tes50e28.10 35.2470 108.8200 -9.94 .5 497 78 9 25 82 48 03.00 35.7500 108.77e0 -9.94 -1.7 558 78 9 30 18:5246.78 35.2520 104.8738 33.18 .5 4p8 78 9 25 33:43:17.24 35.Se7e 306.5990 17.Ge .4 550 78 9 3e 13:14s48.40 35.2170 108.8244 -S.94 0.0 40s 7e 9 35 02:47s54.08 35.7584 108.770s -e.cs .4 See 78 9 34 18e31888.34 35.34es 108.8810 34.4e .5 See 18 9 25 03e11843.00 35.7500 106.7700 -9.90 e.0 541 70 le 1 00:10139.80 35.2430 108.8579 33.88 1.1 Set 78 3 25 93s32:40.30 35.7930 105.7268 19.10 -1.7 582 78 to 1 s!*44s57.10 35.2444 105.8160 37.76 .8 Set 78 9 25 03:44:32.58 35.9090 196.7720 St.4e 8.0 583 78 to 1 11:57:34.18 35.2170 104.820e -0.98 .3 583 78 5 25 03 40s28.29 35.7748 105.7700 13.60 .4 554 75 to 1 18:45106.44 35.8174 104.8244 -S.Se e.e 504 79 9 25 83s57 32.9e 35.745e tes.73ee S.Se .5 565 75 le 1 22s22 19.20 35.217e 106.8200 -9.90 -9.9 505 78 9 25 44801:17.80 35.7520 195.7384 8.50 .3 566 78 10 1 22s34845.30 35.3174 108.8204 -9.94 .5 I 508 78 9 25 04198833.10 35.8520 106.7640 14.10 .8 567 78 te 2 03:03:48.10 35.2174 186.8289 -9.98 .3 507 78 5 35 04:00:44.40 35.7500 108.774e -0.9e 0.4 568 70 it 8 03s11838.44 35.2440 148.8550 38.10 .8 508 78 9 25 04st2e27.90 35.7870 les.7554 35.30 .4 559 78 to 2 e3:3t 56.30 35.2174 104.0364 -9.94 .5 l 589 78 9 35 04 39 05.89 35.7320 108.7270 9.99 .3 57e 70 te 2 11:05e82.70 35.3810 166.0240 -9.98 .4 Sie 78 9 35 04 5ts29.40 35.7800 106.8900 11.49 .3 571 78 10 8 13:05 38.90 35.2174 148.9394 -0.94 8.4 511 78 9 25 9811343.40 35.7500 106.1700 -9.90 .8 572 78 to 3 11:07:35.14 35.2174 104.8204 -9.94 .4 512 78 9 25 06 42801.24 35.8488 148.7348 12.90 7 573 78 se 3 18128:23.80 35.2170 108.8200 -c.90 .3 513 78 9 25 Ges42103.36 35.7700 198.7458 13.38 -9.9 57e 78 le 3 12s20:27.48 35.504e 107.2240 35.te .8 514 78 9 25 ess42st$.'8 35.7564 106.7210 14.10 -9.9 575 7e to 3 17 01:24.94 35.1744 146.8440 28.29 .5 585 70 9 25 86150sts.74 35.75ee 106.7789 -9.9e .8 578 78 to 5 03 14893.58 35.5710 107.2500 3.44 .8 585 78 9 25 06:55s35.30 35.7400 196.7320 11.20 0.0 577 78 to 7 23s13:18.34 36.1114 108.1384 4.80 .7 517 78 9 25 06:58:06.28 35.7570 stE.719e 11.5e e.e 578 70 le 8 17s03:57.94 34.5160 104.1939 22.70 .8 ao 579 78 to 8 17:07 08.90 34.5454 198.1880 14.50 1.2 s stb 78 9 25 07109181.44 35.7668 105.7936 9.=e .4 ch $19 78 9 25 07:17eJ4.84 35.7450 106.7600 14.44 .8 588 78 le le 05:59e49.10 35.4234 104.7838 29.90 1.3 i
52e 78 9 25 07s18 44.50 35.6814 185.7164 10.44 .4 - 581 78 le it 07:34e47.34 35.8800 108.7494 -9.90 e.8 521 70 9 25 00:02142.20 35.7503 106.7748 -9.00 -1.7 582 78 le to 17:58e04.50 35.0304 148.3188 E7.48 1.1 522 78 9 25 00e20st5.54 35.7534 106.7254 8.34 .3 50310 to 11 13:43898.28 34.2948 108.1944 8.86 1.3 523 78 9 25 08159843.00 35.8440 105.7549 13.00 .3 584 78 to 11 44s47st2.70 36.2774 105.9596 7.74 .3 524 78 9 25 19s45s33.54 35.730s 108.7360 g.40 .3 585 78 14 11 15:4te32.10 34.4200 104.9444 -9.90 .5 525 18 9 25 12:28848.30 35.7584 105.1704 -9.90 .4 -
584 70 to 13 e7 43s00.34 34.9284 108.4879 38.80 1.3 528 10 9 45 12:30840.20 35.7594 196.7079 12.04 0.0 507 78 10 18 43:38853.10 35.2524 107.4534 13.84 .3 527 78 9 25 12:37 20.18 35.7500 105.7700 -9.98 -1.7 588 78 10 19 48828e52.30 33.9990 148.3944 88888 1.2 528 78 9 25 12:58 38.50 35.1564 108.7790 -8.99 .4 589 70 19 24 20:04:4e 3e 35.2860 104.1130 10.80 .8 529 78 9 35 15 47s87.70 35.0100 105.787e 8.84 8.0 500 18 to 25 08:37s35.00 35.9604 108.2569 -0.94 .5 530 78 9 35 14:33:18.88 35.8060 106.7284 14.18 .4 591 18 to 29 08155s51.44 35.0544 108.9804 -0.94 e.e 531 78 4 25 15:04e45.30 35.7988 146.7364 11.10 0.0 592 18 le 3e 03158128.84 38.3874 108.5438 11.74 13 533 79 8 28 42:10:31.49 35.750s 108.7700 -9.99 .8 593 78 19 38 45 40st4.to 35.8414 108.8588 9.10 .3 533 78 8 24 42s37e57.80 35.8626 106.7829 9.44 .4 594 79 11 5 00:05s87.00 35.8830 148.5086 33.90 .4 534 18 9 38 15 33122.18 38.asse 195.7548 18.20 .3 595 70 11 5 00s40st4.49 35.7850 198"7200 13.79 .4
, 535 78 9 38 15152e36.44 35.7500 144.7706 -0.90 .8 594 78 11 14 17:46:53.00 35.3454 148.1480 13.54 1.4 538 18 9 24 18 55s24.70 35.8334 168.70 4 8.34 .3 597 70 11 15 16:24:44.40 34.8548 107.1500 48.00 1.4 537 78 8 at 20:19848.10 35.7500 144.1424 18.40 .3 588 78 11 15 23:43:48.94 34.1370 104.33s0 13.40 1.8 538 79 0 88 38s58:05.10 35.7500 106.7700 -9.90 -9.9 593 78 31 18 00:13 50.40 38.1944 198.3480 8.44 .8 539 18 9 28 89s0s:45.28 35.2434 108.03 e 37.te 31 848 70 18 18 88s31:57.30 34.1589 148.1780 7.84 .5 540 78 0 28 14:37s03.10 35.8000 108.1370 13.50 .4 931 78 31 10 03:44:13.4e 38.333e 138.13ee 7.es .8 548 10 9 at 13:18 34.70 35.3400 106.7946 33.16 .8 ett 78 11 18 85111:22.90 34.1300 108.8444 0.44 .3 542 78 9 28 12 50:48.20 35.1800 106.72tt 19.50 1 883 78 13 18 05 12888.34 38.184e 108.2740 5.50 .8 843 78 9 29 10:34e25.5e 35.3358 808.8854 83.00 .5 004 78 11 te 09:38s34.74 30.1150 108.1989 9.54 4.0 544 78 9 at 82s81s49.20 35.2170 106.8200 23.14 1.4 885 70 11 18 13:55113.40 38.1810 148.1500 8.4e .4 1 845 78 5 28 32 10:01.86 35.8174 144.8248 -0.00 0.9 804 78 11 17 83:13:54.00 30.3330 168.1889 8.34 0.0 548 78 9 29 92844e14.10 35.2350 106.8550 19.74 1.1 887 18 11 !? 03:18:25.04 38.1184 108.1849 18.56 4.8 547 78 9 30 82e56456.94 35.2874 145.8204 -0.94 -9.9 Sf3 78 11 17 08 34 e 38.74 38.1196 168.1844 -0.54 4.0 548 78 9 29 99:30s44.50 35.2368 106.8448 25.50 1.7 800 78 18 17 45s50135.04 34.1390 108.1999 11.40 4.4 ;
349 78 8 89 09:47:15.80 35.8298 106.8110 18.99 .3 818 18 11 17 18:34131.70 38.1194 134 1846 -8.30 .3
41.. t o t, teag depth =os quet "* ggn dage glee ten long depth eng staat me ton date Gil 78 11 17 13:05s18.20 36.1189 148.2568 9.06 .8 4.4 574 19 1 28 03st3s34.74 35.5300 107.4784 8.88 1.1 .3 812 78 tg g7 g3:3147.70 38.1289 tes.1378 17.54 673 79 1 28 18 39:13.50 35.3184 188.8878 37.88 413 73 13 18 ees30s54.te 38.1399 106.1844 -9.08
.3 674 79 1 28 18:37:04.04 35.1950 164.8550 33.04 e.0 End 78 11 2e 38 sees 42.84 36.9384 103.9570 assas s.6 4.8 675 79 1 30 15:57s43.70 35.2434 104.8350 38.30 1.7 .3 yg g43g30 88815:47.18 35.1804 100.8884 34.94 885 78 tt 23 05:e8s47.Se 35.7450 106.625e 21.58 $7s 1.0 gy, 79 ggsege38.ge 35.ggle tes.8330 83.40 .8 sts 78 11 25 18823:37.79 34.86ee 145.8440 to.Es 18 373 73 1 31 10:39:37.44 35.1788 106.8554 29.74 1.4 .5 817 "PS 11 28 ess25:38.14 35.2304 105.7418 34.48 .8 679 73 3 1 43s53s19.58 37.9689 107.3674 78.se 1.8 618 78 11 28 13:38 26.e4 38.5750 105.5710 25.70 .7 884 79 8 2 05:26:38.50 34.5710 106.5744 34.34 539 78 12 3 e3s50s23.ee 35.6530 146.8350 te.78 .4 681 79 2 2 tesels35.te 35.8494 104.8594 36.54 1.0 .7 824 78 18 7 e7 e4:31.34 36.1959 146.8294 -9.90 .8 882 70 3 3 37st6sts.58 38.9848 104.7644 30.10 621 73 12 7 2es27s22.80 35.1950 166.8298 34.50 .7 683 79 3 3 18s27841.94 35.8814 tes. Side 31.74 .5 622 78 13 7 23:25s5s.74 35.2854 166.8274 30.13 1.8 434 79 8 3 12:23:17.84 35.115e 106.7004 28.90 0.0 s23 73 33 la 14:15:46.34 35.85t8 103.4434 asssa .5 ses 79 8 3 18:37s33.90 35.1889 108.0190 28.14 .5 .3 634 78 12 13 31s55843.sg 35.e40s 106.4300 51.40 625 78 12 14 09:48s41.90 35.4200 347.3368 -9.98
.3 ggg 73 3 3 12:39s51.49 35.1714 104.8324 34.00 62s 78 12 15 40st5st2.te 35.949e 104.3100 9.20 8.0
.3 887 78 3 5 19 s 54 s 34.30 35.1714 104.8328 -8.9e I
8et 79 8 5 22833:51.3e 35.1484 tes.sase 82.4e 0.0 L
.5
$27 78 12 15 18:59831.18 35.1950 106.8310 35.44 1.8 '
628 78 12 ts 23:06:32.80 35.2708 186.1118 1S*38 .7 889 79 3 5 23:10:38.80 35.1726 104.04 0 33.10 -9.9 629 78 12 17 02859:39.14 35.4550 106.2240 11.2e set 79 3 5 23 10:43.74 35.1890 108.8499 28.78 -9.9 i 830 78 12 17 45s59806.2e 35.1264 146.2830 9.64 1.8
.8 891 79 2 8 19:04838.69 35.1584 106.2844 23.30 1.0 531 78 12 17 06:12:34.20 35.4810 105.2380 15.50 1.4 892 70 3 8 23:09:18.84 38.8718 148.2044 2.44 1.6 .8 Ele 78 12 17 tsst3se2.30 35.877p 3e6.345e 32.60 1.1 693 19 3 6 23:15s08.74 35.2900 106.118e 7.54 1.4
$33 78 12 22 10:27:47.60 35.0364 188.619e 35.88 694 79 3 8 23s23s59.00 35.3520 104.1334 80.34 .5 634 78 32 26 e3:e9:42.48 35.9'If 199.8878 14.88 8.8 1.8 695 79 2 9 49:39:58.30 35.0230 148.2494 9.34 .4 g35 78 12 29 20:44s51.60 35.2800 106.1169 14.36 696 79 2 te 19:34s44.50 35.1644 168.8350 28.94 0.4 836 78 12 30 lastis26;50 34.4430 146.3470 61.se 2.3 697 79 3 to 20s3448.40 35.1484 108.0410 20.58 0.0 637 18 12 3g e4:09:e2.98 16.4100 196.6504 -0.90 .3 698 79 2 to 20s35:02.44 35.1844 108.8514 28.14 1.8 638 78 12 33 14s39:34.69 36.1334 146.2128 7.20 .5 899 79 2 32 08s55s51.98 35.1850 106.8530 45.54 .5
.5 439 79 1 4 16:41:59.64 36.3E70 145.2453 31.2e .7 700 78 2 12 49:23:47.34 38.5000 106.7544 -9.90 64e 19 1 5 22:48s37.80 35.2288 108.854e 51.48 1.1 Mt 79 2 12 12 29:43.80 35.3288 106.0084 19.54 0.0
![ set 79 1 8 07 s 33s 49.30 37.e 450 147.1650 34.20 142 79 2 12 15st7s30.20 35.1978 166.0576 36.74 0.4 N 842 79 1 9 47:19 00.28 35.4750 107.3560 9.50 .8 783 79 2 12 18:40:23.00 35.3430 107.3274 8.76 .7 343 19 1 9 17:42844.30 37.1810 1e9.5789 99.40 1.5 704 79 2 13 02:32s35.40 35.3378 107.3320 0.40 .8 644 79 1 9 19885s53.84 34.99 M 106.396e 24.24 1.1 yes 79 4 13 08:11 05.70 35.*394 107.3734 28.20 .5 545 79 1 12 23:38:18.24 35.3494 106.1820 11.60 .8 748 79 2 13 15:21:09.24 35.1700 146.7939 30.00 1.1 g48 79 1 14 01:43s18.90 35.8908 107.11E0 13.70 1.8 787 79 2 15 04:41:53.30 35.2370 104.8830 40.10 0.0 g47 79 1 18 40s31857.30 35.4300 107.35te 5.18 .7 798 78 2 17 18s58 set.Ge 35.1849 104.8434 21.24 4.4 s48 19 1 17 08:15:39.58 38.25te 108.8148 9.38 .7 749 79 2 19 19:48ste.50 35.1980 148.8174 7.30 .9 849 79 1 17 e2843:38.24 36.6334 143.742e 14.54 12 710 79 2 20 12:53s54.34 35.1520 106.8526 21.10 0.8
$50 73 1 17 80s22:58.80 38.2898 108.7810 8.18 .8 7tt 70 2 21 03:30:57.50 35.1444 108.5410 17.70 .3
$51 79 1 17 11:32s28.30 38.2420 106.7404 8.98 1.4 712 79 2 23 04st3s48.te 35.1390 106.8204 te.it 0.0 1.1 852 70 t 18 00s3ts37.20 36.5589 146.5510 12.66 1.8 .7 713 79 2 23 20:33:25.00 35.1714 108.1140 15.04 853 73 1 18 14:34s17.80 38.5998 106.4388 -9.90 714 79 2 24 02:25s30.10 35.1984 148.8344 38.10 1.0 7 715 79 2 25 07:47s06.04 38.8750 108.8730 9.44 1.1 654 79 1 13 02:24:34.88 36.2669 106.7484 11.08 .8 .8 855 70 t 19 Ste40822.40 35.4659 147.2360 8.74 718 79 3 25 07:57s58.00 35.1964 106.8190 18.14 650 79 1 19 18:54:42.24 36.3320 108.2974 26.4e .5 717 79 2 25 28stes34.50 35.1744 108.8459 31.30 .3 457 79 1 20 14:04se7.lt 35.8600 100.9500 6.49 .7 118 79 2 25 23:13838.90 35.1814 100.0180 13.18 0.8 850 70 1 20 15:17:30.99 35.8288 146.8244 1 18 1.3 .5 119 79 2 25 22:13:50.00 35.1878 108.8540 19.00 0.0 859 79 1 21 tt:44:04.G4 34.8520 108.7190 12.50 729 79 3 1 11:15:40.40 30.1424 108.1544 9.94 .7 880 79 1 21 17:18833.08 34.5540 tag.e974 33.30 .4 721 79 3 1 18 30:54.9e 35.2500 106.9970 11.8e .8 881 79 1 22 20s18st3.Se 35.1914 108.829s 34.84 .5 722 79 3 3 13:24see.te 38.1890 108.8444 10.00 .5 4?? 'O t 24 14:14:31.34 35.1930 108.8230 34.00 .8
.C 723 70 3 5 19818 30.80 35.1984 108.8444 15.14 .3 883 79 1 24 18st3sti.20 35.1050 104.9848 31.40 .3 724 79 3 8 11:33s50.00 35.2004 105.821e 18.2e .5 884 79 g 25 etsState.39 35.2844 146.8854 32.00 sgs 79 3 5 13:08:42.79 38.3778 106.1748 32.00 2.5 805 79 1 25 33 sets 29.50 35.1150 198.8198 9.79 8.4 725 75 3 8 13840ste.40 35.1964 100.6314 30.44 .5 888 79 1 25 03sats54.50 35.19tt 144.03G0 -0.96 8.8 137 13 3 7 gesSts98.60 35.2154 tes.817e 12.6e .7 887 79 1 25 11:18s04.89 35.1880 146.8480 31.58 .8 728 73 3 7 ggeg4sBt.00 35.1970 198.8870 17.84 1.0 tes 79 1 37 00:24:10.18 35.1969 196.7919 29.5e .5 13g 79 3 7 11s03:53.94 35.1630 106.8548 16.94 .5 889 79 1 37 33s47s45.48 35.1880 188.8540 31.78 .5 730 79 3 7 15s00st3.49 35.5848 104.1198 11.00 1.1 i
8?e 79 1 27 49:51s48.10 15.4590 197.5388 14.94 .1 ?)g ?g 3 7 ggsgg 3g,gg 3g,gg7g ggg,373g gg,gg g,g 6tt is 1 28 83:45s48.00 35.2474 140.8250 31.30 .5 733 78 3 9 10:07s58.80 35 1849 108.3990 4.84 10
- -- -- , - ---y.,,-- - _ - - - , , - - - , , , , , , - - - - - - - - . - - - - - ------u "a 8 44*I ** date tet long depth' seg goal me ada dets tame let l'as d*Pth "*f sda stee 733 79 3 to 13:53s24.9e 35.1998 108.7970 18.78 1.8 794 79 4 18 e9:49836.80 35.8170 108.8864 -S.Se .3 734 79 3 11 2181ts22.80 35.287e 106.8200 -9.90 8.0 195 19 4 17 els 40 s 01.34 35.3178 104.880s -9.94 0.e 735 79 3 11 33:53:34.13 35.2120 106.3629 32.40 0.0 796 79 4 17 90 sets 44.80 35.713e 108.898e 9.94 .3 .3 736 79 3 12 99838:38.30 35.1930 108.85te 12.34 8.0 797 79 4 17 testests.Se 35.7820 104.8049 8.54 .8 7eg 79 4 33 43e35ste.at 35.8170 104.880s -0.94 737 73 3 12 ansees45.50 35.0638 tes.2456 7.80 1.5 .5 7gg 73 4 13 eds55e35.88 35.8174 144.0000 -0.8e e.e 733 73 3 13 82s54:13.48 35.1934 168.3470 41.4e see 79 4 13 13 s t 3 s 35.94 35.8 8 70 106.8344 -0. De .4 73g 73 3 13 33st3st?.60 35.1880 145.0200 19.8s .5 740 78 3 15 00s29:24.38 35.1660 106.8330 t?.2e .3 set 79 4 to e3 39s57.34 38.7978 104.4834 59.00 .3 741 78 3 15 ess48s30.79 35.3650 tes.830e 18.te 1.2 .3 383 79 4 2e 38148s33.3e 35.418e 107.t744 11.74 .8 ge3 79 4 2e 33:43:13.80 35.4888 107.2934 8.te .5 748 79 3 15 19:0s:43.14 35.0979 185.3478 20.De 15 304 70 4 to 33s44:18.se 35.4310 107.348e 5.80 .7 743 79 3 17 statssee.30 38.240s 104.3048 14.00 .5 se5 79 4 at 08 00:33.90 38.4544 107.3418 18.84 .0 144 79 3 !? 17st4:33.7e 35.1800 10s.83e0 32.40 1.1 368 79 4 at seest:47.50 35.4388 107.3430 17.90 1.5 745 78 3 13 03s34s58.40 35.1760 105.8100 18.00 1.3 se? 73 4 at 01:34s58.1e 35.434e 107.3404 18.14 .3 746 79 3 19 02:30s50.40 36.4864 105.4360 20.74 .8 Set 79 4 23 00s 43 s53.00 35.317e 104.8800 -0.De 0.4 747 73 3 19 e4 33:54.78 35.1979 108.8950 17.78 .3 3s9 7e 4 34 ess31st5.78 35.3170 108.8804 -9.De .s 740 79 3 21 01:30 855.50 35.2170 106.8200 -9.9e e.4 Sie 79 4 24 18:818 41.50 35.217e 148.890s -0.De .8 74e 79 3 at 02:27s09.19 35.2170 188.0200 -9.99 sit 79 4 34 18850:48.1e 35.3176 164.5200 -3.De .8 758 7e 3 at 03:27 41.54 35.1788 148.7810 20.88 12 .3 sta 79 4 35 05 s 40 34.30 35.3170 108.030s -0.De .s 751 70 3 21 easteset.4e 35.3304 106.349e 23.30 .5 313 79 4 38 03stis55.50 35.2170 1e4.030s -8.00 .4 752 79 3 at 15s54:07.7e 35.1350 188.845e 25.00 1.2 Sie 79 4 27 11:54 13.50 38.8480 165.4934 39.30 1.7 753 79 3 22 ess22see.Se 34.447s 198.9510 45.10 gis 70 4 3e 01:41e23.40 36.3374 te6.740s 8.54 .7 754 79 3 23 18s08s55.24 35.8750 See.825e 20.48 0.07 sta 79 4 3e et e 4 4 s tE.2e 36.3360 106.73 44 s.Se .7 755 79 3 25 09812:06.4e 35.2170 188.3200 -9.00 .3 st? 79 4 3e 03 27s06.00 36.3464 148.7820 8.44 .5 756 79 3 25 12e14s48.18 35.221e te4.8840 21.58 .7 sts 79 4 38 49s 43 set.74 35.5440 1e7.315e 10.90 .7 757 79 3 25 20:04:24.38 38.457e 195.4550 19.98 4.0 819 79 4 30 19:48s04.00 35.217e 108.5200 -9.90 e.4 758 79 3 26 00:2sst9.le 35.194e tes.832e 22.10 .5 324 79 5 1 05:37:43.58 35.8174 146.8344 -0.00 .4 759 78 3 26 04st2 55.Ge 35.5094 1e6.187e 13.38 7 821 79 5 1 1e859 37.80 35.4454 107.0930 22.se .8 764 79 3 27 44e26:25.30 34.4474 146.9510 -9.90 322 79 5 le e5stes27.80 35.2170 188.8200 -9.00 co 768 79 3 27 19805s42.28 35.165e 186.8468 21.70 .5 .5 323 19 5 to 09:28:53.28 35.3174 106.0204 -9.90
.4
.5 e 162 19 3 28 18:49 19.44 35.1834 108.8539 23.40 1.E 844 79 5 11 15stle48.80 35.4270 107.3544 12.6e 1.2 00 783 79 3 34 09:28se2.9e 35.1980 106.8330 17.18 0.0 825 79 5 12 18:20se4.30 36.7890 108.0744 83.00 1.1 754 79 3 3e 09:44se2.00 35.217e tes.820e -9.98 2.2 828 70 5 17 14stee58.50 34.3784 148.5958 5.40 1.1 765 79 3 30 tes41:55.8% 35.1930 106.7970 17.58 327 19 5 23 2e:58s58.00 38.2988 105.7000 11.00 .5 766 79 3 3e tes48st7.50 35.165e 186.0870 23.99 4.4 528 78 5 to 01:03:48.2e 36.1380 107.4tDe 21.40 1.2 747 79 3 3e 11:57:39.20 35.2170 te6.8204 -9.98 0.0 829 79 5 30 21132:35.14 35.4730 108.7584 53.06 1.5 768 79 3 31 47seest3.4e 34.419e le7.98te 20.8e 1.1 333 79 8 1 ele 40159.94 38.5620 148.0564 12.74 .8 769 79 4 1 05:33:14.00 36.333e 106.221e 15.60 .8 831 79 4 2 14:4t:08.68 30.8450 107.0410 40.88 1.3 779 79 4 2 03:43:58.99 35.173e tes.815e 28.50 .4 332 79 8 5 05128:10.30 38.3410 108.0954 16.34 1.1 778 70 4 2 11:17:12.98 35.1918 105.848e 27.80 .3
.8 833 7e 8 3 13:43:38.60 35.4534 107.7580 35.24 1.3 773 75 4 3 17849 58.40 35.132e 188.826e 15.30 !
773 to 4 4 ess44st?.2e 35.135e te6. 33e El.se 1.s si4 835 79 79 s e tieteio2.ee 34.s33e le7.a2?e 4e.se 8 te 18 30858.10 34.010e te7.1574 41.94 tt 18 774 70 4 4 12stese?.2e 35.1590 106.353e 22.7e .5 1.1 175 19 4 4 31 58s12.e4 35.tese 106.8290 13.30 .8 .5 838 79 8 la 18:51841.50 38.8754 100.4700 13.00 774 19 4 7 81s43s50.80 34.4770 te8.3870 38.50 837 79 8 13 et:33:51.48 35.7936 108.7414 9.00 .5 777 79 4 7 43s45s17.00 36.1e10 106.3570 31.34 1.1 338 79 0 15 tesege44.04 34.4330 307.0374 78.40 1.3 778 79 4 7 09s17s97.50 35.7220 100.83E0 12.68 1.4 839 70 8 le ses38839.56 34.5820 104.8784 78.50 1.7 779 79 4 7 13128se4.00 35.8414 108.1530 8.90 1.3 ses 79 8 as essasses.te 34.5114 107.1579 2.58 1.8 184 79 4 7 23e35:39.Ge 35.1984 148.el30 33.48 1.1 341 79 8 22 00833:33.30 38.8300 103.73e0 -0.94 .7 731 79 4 7 23:40 53.9e 35.3450 tes.Sete 17.50 1.4 842 19 4 28 18e17:38.28 38.3500 te6.4330 14.90 1.0 792 79 4 11 41849:55.te 35.1980 tet.8 tee 18.94 .8 843 19 8 38 23:4es37 ge 35.8500 137.4304 14.70 0.0 183 79 4 11 02ettset.se 35.31e4 108.7 tee 14.40 1.4 844 79 0 32 83e18:39.40 38.150s 180.7844 13.80 .5 784 70 4 11 tie 41s24.te 35.330e 106.8150 14.50 .8 845 78 7 8 essoasde.se 34.5800 te4.e354 5e.50 1.1 795 13 4 la e3e40s53.90 35.1784 108.5370 38.ee .7 848 75 7 8 15sS5:04.Se 35.1870 106.7800 14.00 1.4 788 70 4 13 09:33s47.00 35.1780 108.035e 15.te .4 847 79 7 8 87s34e47.Be 35.5100 108.8440 38.10 1.1 787 79 4 13 07138853.50 35.8710 148.1030 7.00 .7 848 79 7 14 00selste.48 35.7330 104.8414 66.10 1.5 788 79 4 13 18:41:41.30 35.317e tes.Itse -9.9e .S E48 79 7 15 10:38:17.20 34.3390 107.0300 $3.14 1.1 189 70 4 13 81831e44.00 35.2174 105.0200 -0.90 .E 850 79 7 15 81sa7ete.80 35.1450 tes.Elde 25.44 .8 79e 79 4 13 22132:35.28 35.217e tes.820e -9.9e .8 851 79 7 19 0e:35:14.1e 35.37ee te3.5800 -9.94 1.3 791 70 4 14 88s41:59.5e 35.3170 106.5804 -0.9e .4 152 19 7 It 08:41:34.14 35.3410 137.8344 33.3e .5 158 79 4 14 13:37s48.te 35.4250 107.969e 32.Be 1.0 953 79 7 31 47 05 38.34 35.3000 te?.47te 0.10 .5 793 70 4 15 13:03e48.30 38.8e44 809.1980 49.te 1.8 054 79 7 31 11s30158.5e 35 1870 100.013e 33.00 .5
4 Ida date time tot long depth nog quel me 3dn date . Llos let long depth oog gwel no
{
955 79 7 34 14 24ses.Se 36.3570 107.3450 12.7s .5 918 7e to 17 05:43s34.00 34.3900 164.889e a3838 1.2 358 79 7 24 13:11:13.34 35.1744 106.0118 19.78 .5 917 79 1e 17 11:00s45.34 34.4350 144.7854 84.04 1.3 357 79 7 26 03 20:18.98 38.8500 106.7584 -9.94 .7 988 79 le 17 15:24:43.50 34.1824 104.5e00 55.70 1.3 858 79 7 30 13:3ssis.40 35.1640 108.8848 17.68 1.3 919 79 le 17 las45s38.04 34.1884 104.D44e 7.74 1.7 359 79 8 1 21 53s38.de 35.330s 107.8500 -0.90 .3 923 79 le 18 se844838.40 34.1670 108.7400 48.06 1.8 see 79 3 2 04s23:17.10 35.3300 107.8500 -9.98 .3 921 79 to 33 e4:23st2.2e 34.10e0 106.66De 48.04 1.3 get 73 3 2 ess5ests.48 35.719e 105.9330 25.00 1.1 922 70 to 15 07s29:37.74 34.004e 108.8494 48.54 1.3 ges 79 8 2 14:15s10.94 36.3344 te?.650e -0.98 0.8 923 79 te is 80 s t2 s ti.Se 34.8588 106.7558 31.1e 1.3 383 79 3 7 Itsesse9.Se 35.914e 106.767e -0.90 .5 924 79 to 19 sese7:24.ee 3s.4tte 105.2950 24.0e .s god 78 8 12 13:03s59.30 38.3468 105.9240 8.20 .5 925 79 le 19 e4:59:48.7e 34.1344 100.Se7e 51.44 1.8 gag 7e s 32 13s43s38.44 36.7300 105.0820 34.88 1.0 924 79 to 19 85st8s08.Se 34.170e toe.eate 47.90 1.1 927 70 to 19 els5E s51.48 34.1854 104.8400 53.34 1.3 I ges 73 3 34 15s58s54.50 38.1918 104.8488 7.48 1.8 367 79 3 15 04s24s48.ee 35.2820 104.7944 24.88 1.2 .8 928 70 to 19 t es 40 s25.te 34.06De 104.889e 30.34 1.3 l
333 79 3 17 09:30:20.00 35.9850 105.616e 27.0e 1.4 929 79 to 18 11:25s11.88 34.0798 108.2870 55.54 .s i seg 79 a 37 18s55:38.00 35.6410 105.9844 7.93 930 79 10 IS 19:30s41.Se 34.4840 104.44e4 -0.pe .3 37s 79 3 17 18 50s20.78 35.8414 146.0840 -9.9e 0.0 .3 931 79 18 19 19:43:44.00 34.094e 306.s430 -g.pe -3.3 !
378 79 5 17 20:44ses.14 35.8944 187.0560 9.10 .5 932 79 le 18 23st3845.98 3e.0044 108.8404 -0.94 1.3 572 19 8 18 ess30se?.se 34.470s 106.57ee -9.98 933 79 te it 23s38s11.94 34.0944 106.640e -0.50 1.1 1 873 78 8 19 13 Se:Pt.88 35.4040 107.7900 19.5e 1.47 934 79 10 19 23:49:33.14 34.0944 1e6.5400 -0.94 .3 374 78 3 te 13:57s20.5e 35.3450 187.7500 24.00 935 79 to to 04 s 58 s 11.44 34.0944 106.6480 -0.De 1.1 3
375 79 e 2e essesst?.30 34.5768 107.8000 -0.98 .5 938 70 te 2e 41s40 22.54 34.4944 106.6480 -e.Se 1.2 f
376 75 g at 11:09:33.00 36.5410 106.6940 7.se 1.0 937 79 le 20 82stes52.98 34.8944 104.6400 -0.9e 1.1 377 79 8 20 12:05s43.10 34.4670 106.7890 4.98 1.4 930 79 to 20 45 s 43 s e8.94 34.0944 te$.4480 -0.De 1.3 373 7s 3 at 21:08:36.28 35.283e 107.5264 5.40 .3 939 79 la Ee e7s34842.14 34.e940 106.8400 -0.94 1.s 379 79 8 22 tes45:53.se 35.749e 184.943e 22.48 1.8 940 79 le 2e 07:37:20.00 34.0944 106.6480 -9.90 .7 .
1st 79 3 23 23:e3:46.74 35.3420 107.5878 7.64 .5 941 79 le 2e 08:42 56.20 34.8624 104.8634 42.30 2.2 att 79 8 25 04:35s42.40 35.4969 107.8834 15.20 1.1 942 79 to 28 12829s49.94 34.8940 106.6434 -0.94 1.2
, 882 73 8 25 44s37s42.50 35.5250 147.1330 e.74 .5 943 79 to 2e 12 s 40 s 49.00 34.0944 104.8438 -9.9e .3 og 333 79 8 25 87s4esas.78 36.este 107.5300 41.00 1.1 944 79 le 24 21:05:35.se 34.8940 106.8484 -0.94 2.2 i e 384 79 e as 15s37 15.90 36.517e 166.5788 6.20 .7 945 79 le 20 22s45:53.90 34.8940 108.540s -0.98 1.1 4 vp SOS 79 8 24 22:53 05.90 36.5410 106.6000 8.e4 1.3 946 79 le 21 18:42889.68 34.e944 106.6400 -9.90 3.1 !
006 79 3 26 23:22:18.6e 36.5104 188.5520 5.30 1.1 947 70 to at 11:20808.00 34.4940 106.843e -3.pe 1.7 087 79 8 as 01s19:43.94 35.5268 107.4410 28.9e .5 948 79 le 21 las20sas.20 36.9244 106.759e 29.90 1.4 j I
388 79 2 3' 17828s29.34 35.4710 107.0000 28.24 1.3 249791021 15:48s00.94 34.8940 146.8488 -9.94 .5 i 958 70 to 21 17:18:52.86 36.es6e 1e6.7404 18.44 300 79 8 31 18s51s34.10 35.5578 106.0360 24.94 .8 .7 I' 898 79 9 1 21815s51.94 36.4170 104.3968 25.2e .3 951 79 to 22 05:10:15.4e 34.0944 10s.843e -g.94 1.5 l 891 79 0 4 10s36st3.Ge 35.5770 106.2290 6.te 1.5 952 70 10 22 05 5e111.3e 34.e944 106.6484 -9.90 .5 892 78 9 5 09:31ste.68 36.3510 145.5320 20.se 1.1 953 79 to 24 et:50s44.de 35.7250 1e5.0210 27.3e .3 j 093 79 9 5 23:24st9.4e 35.5824 1e7.2880 14.10 7 954 79 to 25 03:25:43.se 35.4874 te7.314e 0.84 .5
, 894 19 0 e ess37sts.4e 35.3260 107.25ee 82.20 .7 955 79 to 25 22 s12 10.e4 34.3844 168.9606 75.10 2.5 805 70 9 8 03:45s33.4e 35.0828 105.8879 51.10 1.2 958 70 te 28 15:30sts.se 35.eges les.02ee og,ge e,e See 79 9 13 00:49:18.30 38.4000 107.42o0 -9.94 .7 957 70 10 20 ess55834.50 35.9140 1e8.1870 7.se e.e I
997 79 9 10 01:01:21.00 35.3230 107.6090 88818 1.0 358 79 le as ogstgeog.50 35.ggge ges,7sle 8.50 .4 808 78 9 19 ess39s95.34 34.3410 103.7244 74.64 2.3 959 79 to 28 88822 34.30 35.9468 108.7734 7.34 0.0 000 79 9 20 10s45s34.70 35.799e 196.7000 20.70 .3 960 79 to 28 16:4ts19.04 30.0820 108.745e 12.44 8 90s 79 9 21 02:5544.44 35.7344 108.0080 11.18 1.7 961 79 10 29 essess51.30 38.3564 tes.4444 13.4e .3 Set is 9 21 18:43s08.50 35.7470 148.4950 9.9e 1.1 902 78 11 3 elettet2.00 33.430s 186.112e 5.54 t.E l
802 19 9 22 80se3:38.50 35.940s 104.2028 10.00 1.1 963 79 11 3 86:10:48.60 36.547s les.812e 11.20 .3 943 79 9 22 33:04:19.00 3s.8470 108.9700 14.18 .5 944 70 11 3 37s13:47.94 3a.g340 108.7410 15.54 .3 004 79 9 34 03141:01.34 35.7300 103.9300 -9.94 1.1 985 79 11 3 13:24s42.38 33.5440 108.233e 7.to 1.8 905 79 9 3e 11:53:44.34 34.521e 194.993e 54.10 13 908 79 11 8 42:15:35.78 3e.eSee 108.000s 3.14 1.2
! See 70 to 3 23 15:58.40 35.1784 1e8.7864 34.18 .7 947 7e 11 11 13:13:58.50 38.174e 100.5730 44.50 -9.9 887 75 to 3 83s3See9.38 35.1500 100.78Be 15.30 .4 988 78 11 11 13s20:45.18 33.ge:S 104.243e 42.13 1.3 l
808 79 le 8 10s25s45.0e 38.8800 184.7678 25.30 .8 980 78 11 11 10:37st?.8e 3e.590s 106.7499 14.78 1.3 i, Det 70 to 11 88:35s35.34 37.84G8 100.0780 33.50 3.e 970 79 11 13 88 40ste.30 35.5194 107.313e 3.34 .8 j 510 78 to 11 23:24s53.40 36.834e 106.8480 49.94 .8 971 79 11 13 ses42 set.80 38.3ste 188.5010 48.00 .5 Sit 19 le it 23s55113.78 37.8848 106.4000 27.10 1.3 973 70 11 13 13 50s35.38 34.540s 104.1134 13.34 .7 Ott 70 18 12 las50ste.44 36.1449 tes.72te 15.20 .7 973 70 11 13 21:31:25.00 36.3930 143.7344 11.40 .3 913 70 to 13 85 s a3 5 4.te 35.7490 105.3288 9.84 .8 974 78 11 33 fis50s33.98 30.asse tes 7730 to.ge .3 914 70 to 15 15:25:17.16 36.3ste its.253e 9.se .e 978 79 11 14 ogs43:30.te 35.830s tee.Sete 5.00 .8 918 78 le 17 03:07:49.34 34.3050 108.7474 94.50 3.3 970 '8 11 15 21s4941.34 30.1100 108.7600 31.94 .5 l
1
s ada date 5t** tel t*"8 depu seg quet as Ede date stee les long depth' seg quet es 377 79 13 19 ete54e36.2s 38. test 1 6.7790 22.3e .7 1938 Se 2 IS 09808:43.33 34.4073 104.8790 -5.04 1.2 e !
378791123 44stes23.40 36.45ee 106.7700 15.88 .4 1939 Se a 10 10:23:40.05 34.9581 105.8432 -6.ee .6 c 970 79 11 23 e9:44s00.40 36.7244 105.7330 19.50 14 1840 Se 8 19 15s04:43.13 35.8858 304.4430 -s.04 0.0 e 90s 19 11 33 Best5:59.94 14.e410 106.53Ge 14.30 .8 1043 se 2 31 11 13s10.01 38.3428 104.5257 -5.44 .5 d Set 79 tt 34 15s20 13.80 38.4258 105.725e 7.00 .5 3e42 Se a at 14s58104.18 35.4550 Be?.9434 -5.te 1.8 d ,
set 79 11 34 15:3404.44 36.4598 106.720e 8.84 7.90 .5 1643 Se 2 at 19 :51 e 5 3.07 35. 36 48 107. 3 8 30 -5.00 .5 b t 003 78 11 26 teetts03.Se 38.20ee 804.8140 10 1844 Se 2 25 00:54s09.78 38.8729 184.8863 -5.00 1.3 h !
984 79 11 29 06034e42.3a 34.7354 106.559e -9.90 .5 1945 00 2 26 88814:48.38 35.5524 108.2529 -5.40 .7 c 905 18 11 as 46e30s32.50 34.7350 104.5500 24.80 14 .7 lede se a 27 00stes57.88 35.8964 108.74t4 -5.04 .3 e Bee 79 13 3 23 26s4e.50 36.954e te7.e42e 59.88 8047 Se 3 27 13st3144.53 35.4514 187.3041 0.3e .4 h 987 79 13 e stegeset.70 35.3840 187.5850 10.50 8 3048 at 3 at s i s t e s 55.78 34.5170 104.340 4 -5.04 .5 e ses 73 33 9 18s22s52.19 34.634e te? tsse sagas 1.0 184e Se a 38 18:39:45.13 34.3770 147.4414 -5.ee 2.s c 989 79 18 14 04e55 23.90 34.0470 100.e73e 98.20 1.1 1850 84 3 3 15 24804.21 36.4658 466.6384 -5.ee .5 b .
994 19 at 15 elettelt.70 38.2500 105.9280 -9.00 .5 .5 test Se 3 5 18888s54.01 38 1731 106.8444 -5.00 4.s e ett 18 la 18 11:2849.30 35.215e 146.333e 33.84 8058 Se 3 8 13: s 3 s t i . t e 35.4569 107.3526 -5.64 1.0 h I 892 19 18 18 15s3es24.50 35.7810 104.5004 8.20 1.4 1853 80 3 5 13838s43.33 35.4470 107.3741 -5.00 e.e c 993 7e 12 2e ess20s21.90 35.7790 104.7040 10.78 .7 1854 Se 3 5 17:53ste.17 35.4917 107.4468 -5.00 .5 h r 594 79 12 at ele 34s59.4e 35.7800 104.8850 8.70 .3 1855 Se 3 7 04s5Bs41.74 34.9388 144.e554 -5.04 8.0 e ;
995 79 18 te 04:10:42.70 35.4420 147.3434 12.50 .5 1958 se 3 9 87:55884.39 34.8205 104.5531 -5.00 .7 h 9947018as 44:41 48.54 35. Side 106.7366 6.Se .8S 3457 se 3 11 11:40848.76 34.st37 se7.4437 -5.44 1.0 h 997 19 13 20 05:32822.00 35.9300 106.755e -9.98 1958 Se 3 15 10:00 30.73 34.8318 104.8784 5.e4 1.8 b gge 79 13 2e 04:18s51.50 35.930s 145.755e 2.40 .5 1859 88 3 15 17e53st?.65 35.8434 144.8781 -5.04 .5 e 989 79 12 2e 09:47 13.14 35.9340 106.7558 -9.90 -1.7 test 80 3 18 14846s41.38 35.8141 144.9893 -5.44 .3 b tese 79 12 22 17:20:10.5e 35.7570 tes.sete 6.74 4.8 3041 Se 3 19 43834:31.17 35.8443 134.4011 -5.44 .3 h l test 79 12 Eg 17:34s36.54 35.7679 106.6044 5.30 0.8 1882 80 3 22 ess40st?.e3 34.9007 135.8497 -5.00 3.4 e i teet 79 12 23 23:50:48.90 35.156e 106.8540 11.00 .3 1863 80 3 22 12s45se2.73 35.4121 167.4518 -5.84 .5 h 1993 79 12 24 13:43 39.34 35.St44 tes. stet 28.28 .8 1864 Se 3 26 00:05:31.99 34.4e85 te7.e589 -5.00 .7 b gete 79 12 24 13:54s41.48 35.1890 106.7940 23.90 1.0 1865 Se 3 29 esset:37.68 35.6088 106.4346 -5.e4 .5 h W tee 5 79 12 24 14:e7 01.30 35.1816 106.8298 28.74 .3 1966 80 4 1 02 23s03.54 36.1355 106.1811 -5.00 .4 e toes 79 12 26 22:52 21.00 34.8520 147.4338 43.70 1.0 1867 Se 4 1 21150s45.73 35.4784 107.3317 -5.0 4 1.5 c
.L 1987 79 12 2e e4:49io2.ee 36.382e se5.e54e 8.se .5 te6S se 4 2 18 24 52.37 35.2583 te7.sG24 -5. .9 h o tee 8 79 12 20 8614Ese5.68 36.4284 186.7544 -9.94 .5 1969 80 4 3 10:04se5.41 36.6384 134.5824 -5.08 .E b 1909 19 12 29 44:33se2.Ee 34.3924 te?.ette 8.00 .8 1870 80 4 4 10s58832.47 35.4418 107.4716 -5.00 .3 e late 79 12 29 23:35849.90 34.487e 106.9800 11.Se 1.8 1871 80 4 5 e6e44s51.88 35.8858 144.9809 -5.00 .8 c tett Se 1 1 44s52:19.75 35.0935 te6.7957 -5.08 .3 h 1872 Se 4 5 19104:53.37 33.3375 1e4.8333 -5.04 1.5 c 1912 Se 1 t 05:41:31.35 33.8793 147.9746 -5.ee 2.0 d 15 3473 80 4 9 10:19:e5.22 34.3463 145.8607 7.98 .4 h i 1813 Se 1 5 85s51se2.24 36.1399 106.9435 -5.ee e.8 b 1874 80 4 13 e5:23:14.25 34.e378 147.3617 -5.84 1.0 d te14 SG 1 5 13829 53.14 38.1824 1e8.0495 -5.es .5 e 1875 80 98 44 15 1515tes43s33.2e 35.9094tes,04sg 106.6957 2.7e -l.6 h tell Se 1 7 08:5e827.94 34.8324 543.5154 -5.00 1.4 4 7 1875 07s43.53 35.ge73 7.44 .g.g c 1918 Se 1 0 00st2:43.43 35.7225 186.863e 11.7e 0.4 e le77 80 4 18 15s40se7.s4 35.0728 144.7745 3.00 .5 a let? Se 1 0 13:08:18.02 35.7174 800.9334 -5.00 e.e c 1978 80 4 10 15s25s54.30 35.0010 146.7924 5.88 .8 e lets Se t II at:30s34.lt 35.4923 186.5453 -5.00 .3 b 1879 80 4 18 15:53e23.88 35.0011 104.7814 .Se 4 e 1819 Se 1 17 07:54 eat.57 34.7540 108.3551 -5.04 1.0 b tesa Se 4 at 03s13:04.93 35.0159 145.4743 -5.00 .5 h 1820 Se 1 le 14s40:3s.53 34.4839 tes.2te? -5.e4 .8 e test to 4 23 07:25884.13 35.8790 104.7995 .30 .5 h lett Se 1 39 00:28s43.18 38.8717 105.6533 -5.00 .e c 1803 84 4 33 47stes39.58 35.8944 tes.Sete 3.10 .5 h 1922 80 1 25 tes23 sea.48 35.4554 103.4932 -5.00 1.4 d 1883 84 4 33 47127:48.85 35.0034 104.8841 .se -1.s e 1923 SS 1 31 03:59829.90 35.4042 100.6132 -5.00 .3 e 1084 Os 4 23 09sege45.31 35. Site 184.7089 3.Se .8 h l 1824 Se 2 3 04s36st3.87 35.1 00 148.8385 -5.00 .3 d 8e85 se 4 33 18:34a33.38 35.8848 100.7747 4.ge .3 l 1926 Se 2 5 32st8s42.53 33.8373 107.8053 -5.00 1.5 4 33 1888 84 4 34 e$ stas 37.sg 35.3713 ges.733g ,4e ,1 e.
1936 Se 2 5 13:5e:28.85 35.7183 107.7584 -5.0e 1.3 e 1987 Se 4 34 13:13:40.09 35.0003 108.7051 .se e.e b i let? Se 2 8 12s58827.4 .7 h test ce 4 34 13:11 58.19 35.0000 108.7868 .7e e.e e late te 3 7 31:31:53.es} 35.5294 35.2487100.8035 147.7720 -5.se
-5.00 .5 d 1989 Se 4 34 19:18:33.08 33.3733 103.7784 .34 tete 80 t 9 13:44:10.84 35.5453 107.4585 -5.00 0.4 t lese to 4 34 33e3es33,te 36.00 3 104.7799 5.90 1.4 .1 h
e 1830 Se 3 0 200ete44.16 34.5948 148.8130 -5.00 .3 e le test 80 4 37 ogs49el4.88 35.3733 tee.???g ,gg ,g , ,
te31 Se I le 31898:23.43 36.427e 106.9282 -5.44 13 b 1792 Se 4 37 13:05:54.53 34.1041 104.7731 -5.e4 1.1 e 1 1938 Se B 15 testSI39.95 35.930t 100.0875 5.00 .4 b 8 1993 80 4 28 07:34:01.50 35.8787 100.777e 4.10 3 e h e 1833 Se 8 15 11:30834.96 35.9265 105.9425 -5.se .7 1804 teOS 80 84 4 4 39 Se 01:03848.98 35.3458 107.4449 5.00 .4 g 1834 Se a 15 51:52:37.79 34.0885 184.8348 -5.00 3.3 4
.3 c 1935 Se 8 38 11:50:44.47 34.8925 100.8844 -8.00 1.3 b test es 4 39 esset:55.13 e3:33:17.eg 35.3757 3g,ggle 187.3170 teg,g733 -5.04, g,g g,g ,
1936 Se 3 15 17817861.18 34.0374 1e8.7290 -5.ee 1.1 c 18 If87 80 4 BB ele 83ste.te 35.3733 10s.0758 B.Es 0.0 e 1837 30 3 18 t#stis44.03 35.7377 188.3784 4.14 4 e 1998 Be 4 38 03e45141.38 36.8905 108.0007 1.30 .s e
e $ i depts Ida dele time tot teeg depth seg quet as ade dele %8*e let long **5 agu e t a s
.1 1880 80 7 13 est40sts.88 34.8787 108.8488 4.00 .8 c 1899 80 4 29 06:32s22.11 35.2334 107.3282 -5.00 e 1181 Se 7 14 tas45sts.74 38.4958 104.5452 -5.84 .4 e 1100 Se 4 34 10s22s49.85 36.9545 106.4276 -5.00 1.3 b siga 80 7 18 13:15s44.e4 35.4187 107.3358 -4.00 4 b Stet se 5 1 02:49:53.4e 35.5843 107.2458 -5.00 .8 b c 1883 Se 8 8 14:05 18.53 35.8097 168.8574 -5.00 .1 b igen se 5 t 10:56s15.28 35.7710 106.0822 -5.90 .3 1864 Se 5 13 13:24 s te.43 38.2875 103.3883 -5.04 1.4 4 3183 Se 5 4 13stss33.98 35.7272 104.7759 -5.00 .7 c 1865 Se 8 13 13:33s39.41 34.0157 168.7971 7.84 .7 b 1804 se 5 6 04:49s50.64 35.6897 105.991e -5.00 .1 e 1848 se a 14 st e es s t2.88 35.434e 107.3773 -5.00 .a d i 1895 2e 5 4 e3se4se4.23 35.5958 105.9544 -5.00 .2 m gggy gg g g4 a3e:Seae.it 35.4834 107.3889 -5.04 1.7 b ties to 5 6 09:3ss37.29 34.5254 ses.8358 -5.40 .5 4 b
1888 30,a 14 43stest3.34 35.4512 807.4444 -5.00 4.0 d 1887 se 5 8 13:48s32.73 35.542e 106.9876 -5.00 .4 gggg 30 g 14 83s26s55.43 35.4455 107.3471 -8.00 e.8 d i
stes Se 5 8 18 set:02.87 35.5225 145.9804 -5.00 .8 e ag7e se g 15 0e:00:44.30 35.4388 107.37e8 -5.00 0.0 d stes Se 5 9 14:18:21.02 34.2s3s 307.3279 -5.00 1.2 4 3371 se 8 15 tes50ste.31 36.4197 107.3584 -5.00 .7 b ttle se 5 to 04:01 36.52 37.5584 104.3337 -5.00 1.4 d gggg ge g 30 48 58s48.93 34.8593 147.0075 -5.0e .5 b tttt se 5 13 etste 53.9 35.e128 106.965e -5.40 8.0
.8 h
e ggyj gg g 33 tt:44s33.77 35.4584 107.4888 -5.00 .1 c 1818 se 5 18 47847ste.e7 35.8578 108.e847 .30 ggy, gg g 33 g3:33:g1.84 35.7413 107.1855 -5.00 .4 d att3 80 5 te 08:09:27.33 3s.640s 106.1888 -5.00 .8 e gg75 50 8 83 17:31s37.73 38.4884 148.5774 -5.e4 .3 e
! 1134 Se 5 16 09s11s18.01 35.5572 106.8588 -5.00 .2 e ggyg gg g 3g 03:3344.35 34.7584 108.8875 -5.04 .1 d tats as 5 19 07804s27.51 35.8898 108.6045 1.30 .5 m 1877 Se 9 1 01:19:05.98 34.90s4 108.7480 -5.04 .3 e i 1118 80 5 2e 03:03:29.43 35.8545 106.5763 2.78 .2 b gg73 gg g a 33833 04.55 38.0074 166.1003 -5.04 .5 e i til? 30 5 24 23s55:19.29 35.3775 106.7121 3.1e .5 e ggyg 30 g g 13sggs37.18 36.2894 146.5434 -5.00 .3 e tits 80 5 23 03:5t 14.45 36.5858 105.3317 -5.00 .6 b igge se g 7 ess41s24.69 34.3199 145.87t7 -5.0e .5 b 1819 se 5 25 17s39:36.63 38.2939 106.2183 -5.00 .5 e sist Se c 8 9ss58:31.53 35.5105 187.4434 -5.04 .8 d late 54 5 27 '20s52st4.09 35.8988 tes.7936 6.84 .8 c 1182 Se 9 3 e3:33:33.34 34.1888 .104.5038 -5.04 1.4 b i
~
I 1121 Se 5 27 21s20:39.47 35.8289 106.7904 -5.00 -1.2 d 3:01 se 9 tt 02:07:14.08 35.7219 106.9226 2.Se .5 e I 1822 80 5 31 46stes43.93 34.7238 108.1349 -5.e0 .6 d tige se 9 11 ess57ses.34 35.8844 108.8784 8.00 -1.2 e i
! 1823 Se 5 31 tes20:29.02 34.9183 104.4441 -5.40 4 e ties to 9 11 15:16:53.23 38.4844 105.2573 -5.06 1.1 b 1824 80 5 31 11s58s37.97 15.8094 108.1998 -5.08 .5 b tagg se g tg gasegse?.4g 35.4420 107.3737 -5.00 2.0 s t125 se 6 2 32e41s47.00 35.7556 106.9202 3.44 .2 e g337 go g ig 13e:1s43.55 35.4407 107.4840 -5.00 .2 e
,' stas se 6 3 tes45 33.07 36.4709 145.3453 -5.00 e.e d itse se g gg gge25st5.55 35.4407 107.3929 -5.00 .1 c 1827 Se 6 5 23:53:21.17 34.4848 105.9943 -5.00 1.3 h 3:33 Se 9 11 22 52s42.98 35.4654 107.4141 -5.00 .2 c 1828 Se 4 5 tas 3&s 24.56 34.3306 104.8085 -5.00 .8 b I
Y. 1829 SG 5 5 12:53s44.49 34.3823 106.7289 -5.00 .9 c 1894 at 9 12 19:22:18.12 36.3882 105.6550 -5.00 tagg se e 33 13:21:23.48 36.3039 106.6104 -5.00 2.7
.1 d
b i'
-3
- 30 se s 7 e4:55:44.46 35.8355 105.6947 0.00 .7
- 1892 80 9 la 19:44s44.33 38.5471 105.1888 -5.06 1.2 c 1t31 da e 8 07:44s45.53 34.325e 185.9995 -5.00 9.6 d 1893 80 8 12 21:37s33.72 38.5113 145.1870 -5.00 3.s e 1832 Se 6 13 11s11:43.20 35.9919 105.6697 3.30 .4 e tig4 30 g 33 28s38824.88 34.2006 106.8530 -5.00 .a b 1 33 Se 6 13 11:55s53.78 35.8943 106.67E8 3.98 0.0 e itG5 80 0 12 23:40:38.14 38.4853 105.8811 -5.00 .7 c 1134 Se 5 13 12:00:01.48 35.5785 108.6830 2.30 -1.1 b l 1835 30 $ 15 19:5B804.89 36.041e 106.8835 -5.00 .8 h 1894 80 0 13 00:22:58.67 35.4139 165.6177 -5.40 e.0 d '
gtg7 30 g 33 03:0453.84 35.5833 107.2084 -5.00 .5 b 1838 30 8 18 11:33:48.25 35.9412 109.5215 -5.00 1.4 d 1898 Oe S 15 07s47st3.86 35.8858 166.6257 6.64 -1.8 c 1137 Se 8 18 21:22:37.66 33.1176 102.9834 -5.es .6 d stGB 84 9 15 09814s18.00 35.9008 104.8533 -5.04 .8 a 1838 Se 8 20 08st4ste.93 38.0488 166.1328 -5.68 .4 e tape se 9 te ess39:54.3e 34.834e 146.4724 -5.0e 1.1 b 1139 se 4 23 01:e3:47.97 35.8833 306.7940 .50 .2 c 1241 Se 9 18 11:3947.66'34.1835 105.5579 -S.00 2.3 c 1149 se & 23 01:24:32.02 35.8399 tes.1583 .30 .E e 1282 Se 9 18 15s42822.73 35.9934 146.8864 40 0.0 h 1841 30 8 23 17 44:10.83 35.9101 106.4814 20.40 .3 b 1203 30 0 30 ggst4:44.12 38.3847 105.4752 -5.00 .4 d 1:42 50 0 25 08:11:42.53 35.7733 105.5429 3.10 .9 e 1204 80 9 22 10844s37.01 30.5100 108.4245 -5.00 1.8 d 1843 83 0 25 20:07s11.19 35.9493 105.9625 -5.00 1.3 e tres 80 9 23 ess57:58.24 34.0485 104.8329 8.18 .5 b 1844 80 6 26 03:56s00.03 36.814e 108.4512 -5.00 .5 c 1308 88 9 24 43st4s30.57 38.3290 105.9108 -5.00 1.1 4 3145 se 6 27 00s32847.25 35.9458 306.8573 5.ee -1.1 e tt46 to 62 est47 53.26 35.9%80 106.8286 -5.et -1.2 c 1207 Se 9 24 18:14 44.94 35.5407 106.8552 -5.00 1.1 b 1147 84 8 27 c1:44:29.75 35.9434 308.3343 -5.00 .3 b 1205 80 9 25 07s55s17.31 35.9135 107.5053 -5.00 .4 h 1 1148 Se 82e its28s35,47 34.3786 107.9479 -5.e4 .6 c 1209 to e 35 17:30s33.71 35.9092 148.7023 .Se 1.3 e 140 54 4 El 23:04:1s.30 35.9943 308.4832 -5.00 e 1214 80 8 25 18s31:00.48 35.8083 198.7813 .30 .8 h 1
1850 se 7 F tes24ses.73 34.320$ 106.6413 -5.ee 4 e tatt 80 9 SS 19 sets 85.Se 35.8021 106.7370 .se .9 b 1151 Se 1 20:29:43.05 35.2518 107.3300 -5.00 .8 c 1213 Se 9 at les40sts.30 35.0054 348.8451 -5.e4 .8 c 1852 80 7 7 18:08 35.39 35.35m4 107.2300 -5.00 .a e 3 13 Se 8 25 20s53see.36 35.8015 100.7888 .50 1.1 e 1853 se . 5 83s30ses.27 18 28V4 105.00 3 -E.00 .5 c 3214 Se 9 35 20 07s31.00 35.8750 100.7800 .30 .8 d '
1854 Se 7 le 01:19s45.25 37.5304 104.7185 -5.00 .4 b 1215 50 9 30 05:17:48.07 38.8003 108.8738 -5.44 .4 b tagg 30 g gg ggeggag3.37 38.8970 100.8830 -5.00 .7 h
, 1156 80 7 le 99stise7.12 35.4429 346.1399 -5.00 .3 b g3g? 30 g gg 33804830.99 38.7000 108.0144 -5.00 .3 d 1158 Se 7 13 44s14:19.01 38.7189 200.8397 -5.00 1.8 c 1338 Se 9 3e 13:30:38.08 33.3444 307.73gg -g.ee 1.3 3 til' se 7 13 04:27 33.08 36.7568 10s.8522 -5.00 .5 c latt 84 le 7 11 17s08.37 34.3081 108.3434 -5.00 .3 h 1158 se 7 13 e5s18:53.47 35.7414 108.1304 -5.00 0.0 C 1880 80 10 8 07:30s37.50 35.2803 147.7384 -5.00 .1 b 1859 8e 7 13 ess44:58.88 18.8988 100.04e? -5.00 1.3 h
- 5 tiae let long depth. nog quet es gd, date 41ee let long depth eng quet as ada date te 1221 Se it 8 19:58:47.49 38.4573 105.8502 -5.00 .5 h 1282 Si t 18 13:44:53.88 34.3170 194.7838 -5.60 1.2 .4 b
h 12 1228 Se 18 14 17 s te s 41.50 35.37e3 147.8098 -5.00 .2 d 1283 81 1 to 31stes43.59 35.8888 197.2548 -5.00 h 1223 SG 18 34 17:26s45.84 35.3739 107.5513 -5.48 .8 e 1284 81 1 11 e9:34:13.96 35.5874 107.2317 -8.94 .3 .1 e it 7
1224 Se to 14 18:08:45.97 15.8960 107.4720 -5.99 .3 d 1285 81 I 11 17s24 s ee.80 38.3438 108.8071 -5.De .9 e 8
.8 c 1286 31 3 4 33sefstf.04 33.8248 146.8890 -5.00 .8 d 1825 SG 18 18 ess24843.2e 35.4675 107.5883 -5.00 .3 c 1287 St a 5 05s53:42.30 33.8729 tes. esse -5.04 .8 b 108 1228 Se to 17 24s53s42.20 35.3858 107.5933 -5.40 .8 e 1200 St 3 12 44s51sts.88 38.7434 108.7133 -5.00 .5 b 18 1227 Se to 17 2es54s34.99 35.3242 te7.5520 2.90 8.8 e 1889 81 2 29 13 45s10.38 35.0871 808.4448 -8.84 1228 Se to is 08:17890.42 36.1589 106.1822 -5.00 .2 e 3290 81 2 It ses28s54.88 35.3184 107.7228 -S.De 4 h 8 1229 Se le 19 07 s 24 s ts.77 38.1813 105.1452 -5.0 0 1.3 c 1281 81 3 23 13s4t:38.88 38.0888 104.85e1 9.70 .8 e te 1834 Se le 23 14:37s08.76 34.6253 107.0991 -5.00 .4 h 3293 8t 2 28 08 49447.09 38.8992 304.8831 -5.00 .8 e 3 3231 Se le 25 98821:01.73 35.2523 107.3514 -5.00 8.8 b 1283 81 3 8 37s4te33.34 35.5838 107.4411 -S.to 0.0 .5 h ?
1832 Se le 35 18:42s52.87 35.5430 147.1630 -5.44 d 1294 81 3 8 ets81s20.t5 36.3888 194.8488 -5.04 .8 h e 9 1233 Se te as 13:28:13.83 35.0929 146.8088 3.04 .8
.7 b 1295 El 3 5 12:29 58.84 34.8834 168.8431 *5.64 7 1234 80 te 37 31:33:47.38 35.0688 198.7888 2.00 4 gpgg 31 3 15 12s44:37.01 35.9004 106.4194 -5.90 .1 e 8 3275 Se le a8 12:32:02.13 35.9670 108.0087 -5.00 .4 .4 c 1297 81 3 19 ess37ste.38 35.2212 107.7838 -5.00 .3 h 8 1834 88 13 2 22s54s33.11 35.3328 107.5459 -5.04 .1 e 129e 81 3 20 13:57:30.82 34.2004 148.5589 -5.44 .8 e 8 1237 Se 11 2 23s19:10.98 35.3270 107.5544 3.14 8.4 d 1299 81 3 24 00:57s28.53 35.8562 104.9524 -5.00 .5 .8 c 3 1238 88 11 2 23s39sfe.98 35.3524 147.5735 -5.00 3.3 22 a 8 1238 80 11 11 17:34s34.st 38.5291 104.9821 -5 .30 48 d 4
3300 81 3 24 31s40s52.24 35.5991 884.8834 -5.04 33eg 81 3 3e 13:25:57.52 38.7987 108.8448 -5.04 .8 e te .
.8 1248 Se it 13 39:49sts.24 35.7929 108.3648 I
1341 80 !! SS 21 32:09.21 35.5728 148.1848 1.19 -1.4 e 13e2 31 4 1 02:1739.40 35.3531 107.2649 -5.00 .1 .8 b
b 8
5 1242 88 11 17 21:46s49.81 35.8813 105.3846 7.30 .5 h 33e3 81 4 5 00s40s48.18 35.8758 168.0203 5.00
.8 e gjg4 51 4 5 44s40s55.74 35.8893 148.7887 .30 .9 h $
l 1243 Se 11 18 13:21st3.94 35.8859 106.1128 3.70 1.10 .2 e g3p5 31 4 5 04:14s15.12 35.8634 108.8135 5.00 .1 eh 139 1244 80 11 18 14:22:52.55 35.8933 106.6912 1245 Se il 18 14:29 44.35 35.3451 107.5914 -5.80 .1 c 1388 81 4 8 13:34s49.32 34.1819 106.9778 -5.00 14 1248 Se it 18 14s32:38.11 35.4147 147.6901 -5.08 0.0 .2 c 1387 81 4 8 22 23s55.21 38.8409 105.2954 -5.00 1.0 d it 1247 80 11 18 15:30s43.63 35.3580 107.5254 -5.00 c 1348 81 4 17 13:36s45.90 35.3311 188.9878 -5.04 1.5 .7 c
e 13 9
1248 Se 11 18 15:35:20.73 35.4247 107.7183 -5.00 .5 e 1389 St 4 18 01:51 set.89 35.1843 308.4155 -5.00 d 13te 81 4 18 12:05:47.18 35.1512 107.9947 -5.04 4 c 8 1249 80 11 18 18:02:10.70 35.3328 107.5718 4.00 .3 C0 1250 SS'11 20 02stis24.83 38.8410 105.7957 -5.04 .5 e 1311 Il 4 13 essees43.78 38.3763 106.3752 -5.94 .2 b e
3 7
', 1251 Se 11 20 47:52s90.41 35.3487 107.5931 3.30 1.4 .2 b b
1312 St 4 to 14:44857.67 35.8698 108.7641 0.00 tot 1313 51 4 22 98851852.50 38.8445 108.Se85 -5.94
.3 c le n3 1252 88 11 22 00:18:28.21 36.3474 148.9662 -5.e4 .5 .4 b 4 1253 Se il 27 49s28:18.29 36.4255 105.5880 -5.44 1.2 b 1314 81 4 27 41:12 58.30 34.5338 107.1489 -5.08 1.4 1254 88 ft 29 08:19:48.91 35.4264 105.5389 -5.94 b 1315 51 4 28 23:58:37.99 34.9834 148.8739 -5.00 .3 hh 135 1255 84 11 30 07s20:34.28 36.5604 146.5557 -5.99 4 b 1338 81 4 3e ess33832.16 3s.9556 106.6844 -5.8e b 8
!?58 Se 12 4 11s40 54.75 34.4458 105.8849 -5.04 .8 b 1337 81 5 I 48s4e802.82 35.8121 107.6483 -5.04 0.4 .4 a 3 1257 84 12 11 12:04882.73 35.8218 187.2644 -5.34 .8 c 1318 88 5 2 17:08:19.37 38.4494 146.5959 -5.00 a 7 1258 84 12 13 ess57868.44 35.4478 108.6240 -5.00 .3 .1 d 1319 St 5 3 14 38s39.17 35.5535 106.1991 14.20 .6 d 5 1259 Se 12 13 09:23s48.29 35.5904 107.2131 -5.00 c 1328 51 5 6 #5 41:24.30 38.6418 164.7525 8.80 1.0 .3 8
1280 88 la 13 16 51844.78 35.5284 107.2245 -5.44 0.e c 1321 81 5 8 11:E7s27.19 33.9428 108.9717 -5.00 4.4 eh 4 1281 30 12 15 11 12:19.02 35.6017 107.2358 -5.00 .5 h 1322 51 5 8 21: 31 s te.88 35.5178 147.3851 -5.04 d 9 1282 SS 12 15 20:57:50.58 35.8209 104.2780 -5.00 .1 c 1323 31 5 9 12 35852.01 33.9770 107.2159 -5.64 2.9 d 4 1283 SG 12 17 09:27:29.72 35.8782 106.6797 3.00 .5 e 1324 St 5 9 12s55:43.38 23.9918 147.1881 -5.60 1.0 .9 8
1284 Se 12 18 17sttelt.Se 3s.3738 105.1239 -5.40 .1 e 3325 St 5 9 15 44:33.08 33.9883 107.0068 -5.44 e c $
1285 Se 12 23 42802s50.05 35.1422 107.1897 -5.00 .5 c 1328 81 8 to 03:40s48.63 33.9815 164.8945 -5.00 .9 1244 38 12 23 93st8s08.42 35.7572 108.8809 -5.46 .8 b 1327 81 5 11 17:05s49.35 35.5845 147.3858 -5.94 .1 b c
7 8
3287 80 12 24 11s57s27.25 38.4479 106.8414 14.5e .1 b 1328 81 W 11 18:43s39.44 35.5271 107.3367 -5.00 .8 c
1268 e4 12 27 22stes48.69 38.3005 108.8494 3.94 .1 b 132g St R 17 83843sts.12 34.9818 105.8390 -5.00 1.2 to b 1330 81 5 20 18:38:47.93 37.1618 106.8356 -5.00 e.e .9 c 9 1240 80 la 28 14:17:43.39 35.4183 147.3253 -5.00 .8.9 4 8279 81 1 1 08:50s37.34 35.5441 107.3079 2.te e 5 1331 81 5 31 02s25s00.84 35.5986 107.3101 -5.49 b 1271 81 1 1 03s58:10.32 35.5388 108.8859 -5.e4 -1.2 b 4 1332 31 8 4 23 50s43.62 35.9994 1e8.8380 -5.68 1.2 c b 18 1272 81 1 2 84:58s95.88 35.4068 307.3504 12.30 .3 b 8 1333 81 8 8 02:38:17.15 35.8098 1D4.7883 84.94 .5 4 1273 51 1 3 45s44s44.38 35.4224 107.3720 11.30 .3 h 9 3334 St 8 8 eas52sS9.89 35.8912 168.7854 5.00 -1.3 eb tt4 1874 It 1 5 09:35835.34 35.4128 107.819e -5.se .3 d 5 1335 gt 4 11 22st4s59.48 37.3896 107.3033 -5.00 1.3 4
1875 81 1 0 13:30st3.35 35.8999 108.5898 .30 .5 c 8 1338 81 0 15 12s20se3.44 35.7492 106.5593 -5.00 -1.1 be 1370 St 1 19 e4s35:47.09 15.3800 397.g331 -5.04 .8 b 5 1337 83 8 14 e5 stas 47.85 33.9764 107.0727 -5.00 1.1 le 1277 81 1 14 44 30st4.59 35.3574 107.9059 -5.0e .4 c 5 1338 Og 8 ge ogst3:37,7g 34,e317 147.05E5 -5.00 .5 c 8 1278 81 1 le 04:5 8 s 07.88 35.3749 107.94e3 -5.00 .3 c 4 1338 Og 8 18 05:40s59.04 33.9853 107.0378 -5.00 1.5 c 9
- 1349 88 8 18 06:40s45.30 34.0155 107.0356 -5.48 .5 c 5 1279 Si t it 05:18885.94 38.3789 107.9283 -5.46 .1 k 1341 81 8 to 00:49:48,88 33.8811 135.8178 -5.69 1.8 c 5 1884 81 1 18 45823:41.50 35.3384 107.9495 -5.00 9.9 b 4
.2 4 1881 81 1 19 64 35:58.54 35.4953 147.8363 -5.00 .8 h 11 1348 81 4 28 44:37859.70 35.4829 106.7955 -5.90 h l
t I
Ida date Lise let long depth eng quel ne ten tong dept $ meg quel ne sdn dets ttee 1343 81 8 48 89118 31.52 35.7279 100.8491 -5.00 .9 e 5 3344 et 7 3 09:08838.33 34.5075 107.1211 -5.40 .7 b 7 1484 81 11 1 es:40e38.95 37.3854 IWS.3847 5.e4 1.5 e h
to 1345 81 7 8 ele 87s33.30 37.3012 107.1889 -5.00 1.7 .8 c 8 5405 et it t 08:38s40.98 35.4398 108.1143 -8.04 .4 e
to 5
1345 El 7 14 85110 43.98 38.t354 102.8855 -5.88 .3 d 4 assa St at 3 09:08:40.01 38.4178 104.8744 3.40 .I
.7 e 8 1347 El 7 17 84steset.45 35.5255 107.4004 -5.00 c 8 1487 81 18 5 08:40834.04 35.3817 148.3848 -5.00 .1 d 3 13t3 81 7 19 18:39808.16 34.4912 107.8733 -5.00 .97 b 8 1488 81 It 6 13:33e58.98 38.8498 197.3457 -5.00 1.5 e 14 334s 81 7 19 19:47s38.35 34.4897 807.1848 -5.48 b e 1409 at 13 13 40e50815.55 38.7185 106.7175 -5.88 b 1356 81 7 to 08815:43.9e 35.3537 107.8558 -5.08 .24 h 5 84te 81 11 11 04:58s20.53 38.8754 148.8878 -5.00 .9 .5 h to 8
1351 81 7 Se 22 55829.37 34.5t 4 8 87. t 345 -5.48 b 3 sett Si 18 12 23s35114.75 35.4534 187.3298 -5.08 c 7 1352 81 7 21 17:58845.81 34.7435 te6.4Get -5.08 .2 b 5 1482 Et 18 13 13:30:57.54 35.4000 107.360s -5.00 .1 .3 c 3 1353 81 7 24 08:11:51.50 34.43t$ 107.9679 -5.00 .9 d 9 1483 81 11 to 07:53sti.93 35.3300 107.8885 -5.00 .7 c 3 1354 pt 7 as 19 10sts.49 34.817e 105.6670 -5.00 .5 b 4 3484 81 11 20 08:45s33.09 35.3486 147.7373 -5.08 .9 c 8 1355 81 7 29 tes4es36.35 34.4653 807.1478 -5.44 1.3 L to tels St 11 as 10:57s43.78 34.8804 1e0.1837 -5.04 .7 b 8 1358 81 7 38 60:43s14.08 35.7349 108.8708 -E.00 .1 e 4 1438 et 11 at 15:44sde.81 34.4418 164.7838 -5.00 .58 1.2 e 13 1357 81 7 3e 09:47134.95 35.7451 108.6548 -5.00 -3.3 b 3 1417 et Il 24 08:51819.88 35.7452 104.7588 c 4 1358 81 8 3 45811:43.88 35.8939 188.8388 -5.84 .1 e 8 1418 Si il 28 04132s28.31 30.7843 144.7788 -5.44 .9 .4 e 5 1359 81 8 4 2e:41:54.95 34.9374 105.6800 -5.00 .8 b 7 1419 St 11 as 09:49 25.87 38.8868 188.6860 -5.00 .9 c 8 1350 El 8 4 21:27st9.47 38.5732 105.1945 -5.00 1.5 .I e 3 1440 81 il 29 84s32 27.40 34.8487 147.0071 -5.64 1.1 d 5 1351 81 8 5 01829814.94 38.3348 108.9647 -5.48 .9 c 11 3421 SS 11 3e 01:57s41.84 35.0008 103.2875 -5.ee .3 c 5 1383 et 8 5 01:44:30.90 36.3449 109.e460 -5.00 2.1 c 7 1422 Si 11 3e 17:30st?.39 35.3658 107.7804 -5.e4 2.0 h 11 1383 81 8 5 03s19s58.94 36.3272 100.0298 -5.40 t.8 e it 1423 81 12 1 23:34s35.95 34.3788 108.8731 -5.44 .5 c 3 1364 31 8 5 18840s47.36 38.3518 149.8498 -5.44 1.1 d 7 1424 St 12 3 09:54s14.08 35.8088 148.8854 -5.00 1.4 e 18 1365 81 8 8 01:12 17.58 37.1571 187.2334 -5.00 .1 c 11 1425 88 32 3 20:19810.62 35.3848 107.8895 -5.84 3.1 d 11 1368 81 8 12 12:29:24.93 36.7598 105.9981 -5.04 2.4 d 3 1428 81 13 4 88s51824.23 34.4798 108.0223 -5.00 b 8 1367 81 8 14 02:06:58.68 35.2722 387.8249 -5.00 1.4 c 31 1427 81 it at 44stes24.95 34.3848 108.7957 -5.00 .5 1368 81 8 14 02:31135.99 35.2229 107.8802 -5.00 d it 8428 St 12 23 e7s44:38.85 34.4548 107.4978 -5.00 .84 c 4 5 3
1369 J1 8 14 02:27:25.98 35.2308 107.9148 -5.04 4 c 4 1429 31 12 23 00:50840.14 34.518e 147.1878 -5.00 .5 d a 1370 81 8 14 43:24s23.41 35.2941 107.8635 -5.64 1.2 .3 h & 1434 88 12 23 21:06:24.14 35.5247 105.8573 -5.84 h 3 1378 81 8 14 08:04:13.54 34.5e 41 147.1844 -5.00 .7 h se 1438 St 12 25 #8s tes24.33 34.3807 305.8438 4.94 .2 4 7 CD 1372 81 8 19 Seetss29.45 38.5839 105.5889 -5.e4 c 9 1432 81 12 27 80s59847.St 36.2063 107.1987 -5.00 1.1 1433 81 12 29 18s21:48.97 35.5100 106.1393 -5.04 .1 d 4 8, IJ73 81 8 26 04883858.04 24.8253 105.7882 -5.00 .74 b h
9 1434 81 12 3e 00:37:19.53 34.3891 106.96t1 -5.00 4 h 4 u, 1374 81 8 27 11e 49e57.53 35.8947 106.7275 7.90 3 1435 81 12 31 18814:34.52 36.4974 108.5608 -5.00 .3 c 9 1375 81 9 i 01:27s54.06 37.1418 107.3759 -5.e4 .9 d to 1936 32 1 6 19:35 21.17 38.1444 108.5588 -5.84 .2 c 6 1378 81 8 7 02:57s23.24 34.9712 186.9978 -5.00 .1 b 9
.a 1377 81 0 9 21:4te49.07 38.5942 146.7359 -5.e4 1.1 b 9 1437 82 1 8 20:54s48.29 38.1838 tes. Esse -5.e4 e 9 1438 82 1 11 04st3s22.99 35.1918 106.6493 -5.00 .5 h 7 1378 81 9 te 05:21:05.15 35.4329 187.3789 -5.48 .E c 12 1439 82 1 12 47e18855.96 34.57 49 100.2125 -5.00 1.1 d to 1379 81 9 to 85s52 53.34 35.7233 106.0668 .It .2 c 5
.1 138e It 9 le 09:54823.49 35.4087 187.3325 -5.08 0.0 d 5 1443 82 1 12 21:35:59.99 35.9899 104.5875 -5.00 d 4 1381 St 9 11 17:49 14.14 35.8841 108.7468 .50 1.1 e s 1441 82 1 21 09:24814.87 35.2493 107.9738 -5.00 .6 d 9 1302 81 9 11 18848:07.47 35.8618 100.7851 5.00 .5 b 7 1442 82 1 28 47e41:41.20 34.e317 104.7220 -5.00 .8 h ?
.5 s 1443 52 2 3 08eE7831.03 35.4484 100.2035 -5.44 .9 c 3 1383 81 9 11 20e28e59.98 35.8614 166.8242 5.00 e 1*44 82 2 4 44st4:59.98 37.2468 107.4100 -5.44 1.4 c le 1384 81 9 11 21 19810.89 35.4365 108.7688 -5.00 .8 c 5 1445 82 2 7 23:12:45.47 35.4889 147.4018 -5.04 .34 e se 1305 81 9 11 21:25 14.34 35.8549 106.8232 5.08 .3 e 4 1446 82 2 11 03:15151.30 37.3394 147.2874 -5.00 h 3 1388 81- 9 14 19:51:34.84 38.8177 108.7584 -5.00 1.0 h it s447 92 2 13 14 42119.97 35.1337 104.4500 -5.03 .7 d 5 1387 81 9 15 Ste28 24.59 38.3355 108.9285 -5.e4 1.2 d It 1448 82 2 18 e8:03:11.48 36.7791 108.8482 -6.00 .4 b 5 1388 81 9 16 03:48:52.49 33.8320 104.9769 -5.00 1.9 d 11 1389 81 9 18 e4se4:58.06 35.e343 165.1442 -5.00 0.6 k 3 14'O 82 2 19 15858e35.09 37.4293 144.3748 5.00 1.1 d 3 130s 81 9 17 41 33st3.58 35.3240 107.8008 -5.88 .5 c s 1450 sa 2 21 16:43:38.88 35.6050 107.2588 -5.00 .1 c 9 1451 82 2 22 tes47:32.37 35.4 33 te7.tS48 4.Se e.e7 c 4 1391 et 8 21 04stese3.72 34.5403 186.6027 -5.00 4 h 18 1452 32 8 24 et:37e35.07 37.4435 107.3567 5.00 c 3 1392 81 9 24 62st5s58.99 38.5341 105.4788 -5.00 4 a le 1453 82 2 28 20:23 58.93 35.1583 104.7531 5.te .8 b 7 1393 81 9 37 82810s42.57 34.5342 148.1479 -5.00 .9 4 7 to 1394 81 9 29 et:50ses.95 35.3334 107.8739 -5.00 .8 b 7 1954 82 2 28 41887s21.48 37.1834 147.3435 -5.00 1.8 d 1395 81 to 1 47848:22.79 35.5334 148.4553 -5.00 .3 h to 1455 82 8 28 40 s e8 s a?.87 38.4478 148.9388 4.74 .3 h a 1398 88 to 14 35:4 esse.41 3g.es37 te?,gyag .5.00 1.5 c 5 1458 82 3 28 18s51:35.18 37.3318 304.8742 -5.00 1.1 b 11 1397 81 to 18 11:28s34.42 35.3744 167.3430 -5.0c 4 h to 1857 82 2 28 tes34s46.47 36.7314 188.7648 -5.44 1.7 c 13 1348 El to 19 84:41s33.27 34.4858 108.e38e -5.e4 .8 d 5 3458 88 2 at 19s58sts.3e 34.7313 108.8e58 -5.00 1.8 d 7 1399 81 to at 03:30e87.43 34.0059 104.15e3 -5.00 4 h 5 1459 82 3 28 21843131.58 34.e544 148.87t8 -5.00 1.3 d 4 1488 81 le 21 03:41843.44 38.4058 108.8542 -5.00 1.1 e 18 1480 82 3 28 23ss3:48.Gt 34.7see 107.93e5 -5.00 3.3 d la 1481 81 18 25 02:44ses.82 36.9547 108.7875 -5.80 1.1 d 4 1481 82 3 2 18845:00.81 35.0110 145.3888 -0.00 -0.8 d at 8
1448 Si to 28 e3:00:51.13 35.7839 tee. stet 4.10 .4 b 3 1884 82 3 8 18:05:19.54 35.8476 105.3174 -5.00 3.9 c 1483 81 11 1 48s14:55.45 30. eses tes.Stes -5.00 .8 h 8 *453 83 3 3 18:14:05.04 34.8491 108.8578 -5.00 .9 c e test 82 3 3 18:39:49.01 35.4738 100.9457 -5.00 .5 c le
idn date ties tat tent depth met guet na Eda date Line tot toeg depth' eeg goet as 1465 88 3 2 16s45s58.99 35.884e 105.3277 -5.00 .9 h 5 1524 82 5 le 31stesbE.47 34.e648 toe.??te -5.04 1.3 c 7 1468 82 3 3 Ste34s37.44 35.8444 105.1892 -5.00 .5 c ? 1527 SE 5 18 88158s37.34 27.1983 187.3167 -5.04 1.7 c to 1487 84 3 4 ete55s23.75 35.5666 187.3800 -5.00 .9 d 31 1528 82 5 to 18:08:48.04 38.85tB tes.8134 -8.44 .7 d 4 1448 03 3 4 49:44 17.87 35.9882 105.3049 -5.00 .9 c 7 1529 83 5 18 13 s et e 34.83 34.88 8 8 148.7139 -S.64 1.8 h it 1459 82 3 5 92103s52.18 36.7348 188.7178 -5.00 1.7 c 33 153e SE 5 IS 13 38808.18 38.8288 148.7144 -5.44 1.1 c 4 1470 82 3 8 e3s47 25.83 36.4809 148.5573 -5.Ge .9 's 5 853t 82 5 18 18eeds57.47 38.7857 408.7868 -5.04 3.3 h 8 1478 82 3 8 43s5te43.64 36.7226 106.7384 -5.00 1.3 c 8 1532 83 5 to 3 8 s te s 53.43 38.8888 tes.7470 5.00 g.7 e 33 1472 83 3 8 15:4e:01.72 36.5845 108.5919 -5.00 3.2 b 9 1533 82 5 18 18stes45 17 38.4477 144.1145 -5.00 1.5 h 5 1473 82 3 7 ess47st6.44 38.suB9 105.6544 -5.08 1.1 b 8 1534 82 5 18 17:30e56.tt 38.5000 108.7898 -0.00 1.8 c 3 1474 82 3 7 ese17s09.15 34.6864 106.6695 -5.40 3.1 d 3 1535 81 5 le 19:54:49.38 36.8488 te8.4PS5 -5.44 1.3 e 8 8475 82 3 8 02:18sta 88 36.7543 106.8458 -5.80 .7 b 8 3538 82 5 18 80st4:21.54 38.7084 106.7381 -8.00 1.8 d 8 1478 83 3 18 11 03e48.45 35.5885 143.4704 -5.08 2.1 e is 1537 83 5 18 atetsses.94 36.8325 108.6058 -5.00 2.s c 8 1477 83 3 38 11845s28.48 35.7181 103.3592 -5.00 1.5 d 8 8538 82 5 16 21sS3857.St 34.0462 106.8384 -5.Se 3.6 s 8 1478 82 3 18 12:24 49.60 35.7719 183.3488 -5.0e 1.9 d 8 1539 82 5 18 81845101.38 38.8382 108.9804 -8.00 3.8 e 8 1479 82 3 IS 23:49:28,88 37.1245 107.3634 -5.00 3.1 c 6 1540 83 5 38 31850sts.41 34.1958 164.0448 -5.84 1.5 c 8 340e 83 3 33 23:34s04.28 36.64t4 108.8505 -5.00 1.8 c 4 1548 82 5 to P2141888.18 34.8231 108.7651 -5.04 1.3 b 5 3481 02 3 24 42s53se2.52 35.8563 105.1274 -5.08 1.9 d 5 1548 82 5 18 22:0244.58 38.0180 168.8650 -S.04 3.7 e ?
1482 84 3 26 e4 17s05.56 37.3847 104.3535 -5.04 .9 d 4 1543 OS 5 18 28108:45.30 38.8498 104.7475 -5.04 1.8 b 5 -
l 1483 82 3 27 19:50s20.e4 34.1613 308.e623 -5.00 1.4 d 8 1544 82 5 14 88 36857.87 38.8158 108.7344 -5.00 .8 h 4 l 1484 82 4 1 44823s33.22 37.1235 107.2825 -5.00 1.2 e 1 1545 88 5 18 23 42 51.71 38.8404 168.9311 -5.08 3.8 e 8 1485 82 4 5 18:43 09.04 34.1425 106.7848 2.4e .9 h te .1546 88 5 18 23:38 Re.e4 36.4578 104.7488 -5.00 1.3 4 4 1488 82 4 5 34s26e28,93 34.2317 106.6831 -5.00 1.e c 8 1547 82 5 18 23:34:15.48 34.88 3 164.8848 -5.e4 1.5 h 8 1487 82 4 5 15:5ests.5e 34.8527 105.7052 -5.00 .9 b 7 1548 OS 5 18 23:35:28.79 36.0448 104.074e -5.64 a.e c 5 1488 82 4 5 18:48 49.13 34.1684 1e6.1450 -5.00 1.2 h 7 1549 88 5 16 23:47e57.08 38.7309 164.7944 -5.04 1.9 d 8 1 1489 82 4 6 08:31:24.27 34.1943 105.5374 -5.0e 1.0 h 7 1558 82 5 17 00007:48.59 38.8474 104.7448 -5.e4 1.5 d 8 1494 82 4 s 4e:50:38.38 34.1448 106.6725 -5.00 .4 h 7 1551 82 5 17 eestes55.27 37.216e 1e7.5599 5.00 1.4 d a 1491 82 4 6 18853s21.57 36.3392 104.7815 -5.00 .3 h 8 1552 52 5 17 90:32 12.04 34.8448 108.8800 -5.00 1.4 c 5 1492 82 4 8 22:16:08.29 34.1221 106.7341 -5.04 1.3 c 9 155 82 5 17 40e33828.21 38.5688 105.8387 -5.00 1.3 c 4 D3 1493 82 4 7 33s31s43.11 34.0024 105.7420 -5.00 .8 c 4 1554 22 5 17 84142s49.40 34.7810 148.8331 -5.00 2.5 c 7
'o 1494 82 4 8 1582425.62 37.0730 107.2692 -5.00 1.2 c 7 1555 82 5 17 00:49 e 34.52 38.8300 144.7136 -5.00 1.2 c 4 43 1995 82 4 8 17 38:30.93 35.5280 148.1796 -5.04 1.0 e 3 1555 82 5 17 04:50855.73 38.0058 107.4219 -5.00 2.3 c 6 1496 82 4 8 22 01 53.49 37.e58a 137.371e -5.te 1.0 h 5 1557 82 5 17 01:04:52.88 38.8542 108.8988 -5.00 1.3 e 5 3497 82 4 8 22:21:41.2e 34.1439 104.8920 -5.00 1.e b 5 1558 32 5 17 e182e813.43 34.8588 104.7183 -5.00 .8 d 4 1498 82 4 9 23:21:29.07 37.2652 187.3275 -5.44 1.1 e 7 1559 82 5 17 41:54e11.89 38.8435 108.8978 -5.00 1.8 e 7 1499 82 4 to e8 34ses.66 34.1739 108.7289 -5.00 1.1 b g 1584 82 5 17 02:1144.48 38.6462 108.5005 -5.00 1.2 h 5
' 1500 82 4 11 15 03:34.47 34.1860 108.7458 -S.se 1.3 h 3 1581 82 5 17 etel3 ell.30 38.6848 144.7898 -5.00 .5 d 4 1541 82 4 15 20s16:56.04 35.1247 107.8769 -5.48 1.3 d 4 5562 82 5 17 eas28sti.57 38.5724 168.7107 -5.8e .8 h 5 1502 82 4 15 e5:47se2.73 34.2 ell 103.e994 -5.00 1.5 c 4 1583 82 5 17 02137ee8.32 34.8534 104.7170 -5.se 2.9 h 8 1503 82 4 18 47s09:03.79 34.1483 108.7026 -5.e4 1.2 b 5 1564 82 5 17 43:48:05.e4 38.8831 108.7719 -5.e4 2.8 d 7 1584 32 4 17 ass 31s24.53 37.0685 187.2542 -5.00 1.2 b 6 1545 82 5 17 ese20:44.se 38.steg 168.887e -5.00 .7 h 5 15e5 82 4 18 e3:23:37.27 34.1374 106.4952 -5.00 .8 h 6 1588 82 5 17 14:38144.05 38.8277 106.8531 -5.00 1.4 h a 1508 82 4 18 e4:4Gs36.43 34.4931 105.1739 -5.00 1.e e s 1567 82 5 17 11:35s58.24 34.e823 108.84a8 -5.00 1.8 c 8 1547 82 4 ts 05:40st?.23 35.8049 105.3258 -5.00 .9 h 8 1588 82 5 17 11 38:43.31 38.8281 138.830s -g.04 .9 c 5 1508 et 4 19 47:34s47.45 38.3134 105.8019 -5.te .9 b 7 1588 32 5 10 essesses.44 34.0008 108.9001 -5.84 3.8 e 8 1508 82 4 19 14:33:38.13 34 14e2 108.7593 -5.00 1.E b 9 1570 82 5 18 e4:08:38.83 33.98 48 108.e494 -E.00 2.7 d '8 1514 82 4 22 tes30e52.9e 34.1841 106.6556 -5.se t.1 b 7 1571 82 5 le 19s35s34.28 34.8338 tes.7e:S -5.00 1.3 b E 1511 83 4 24 e4stase7.95 35.14e5 108.8978 -5.e0 .3 b 7 1572 82 5 18 08:5e:18.94 38.4297 108.8502 -5.e4 1.7 b 5 1512 83 4 25 09:34e02.9e 35.8814 306.8451 -5.00 .R c 3 1573 82 5 le 07:03:48.73 33.8833 134.7340 -g.ee g.4 e 8 1513 32 4 38 15:05s18.77 34.838e 107.7750 -5.00 1.3 d 3 1574 82 5 le 09:09s57.78 38.s783 108.8420 -5.44 1.5 b 5 1514 83 4 23 04 e 3e 15 4.45 3 4.1173 108.7222 -5.00 1.8 h to 1575 84 5 10 ege3te53.84 30.8444 1e0.0927 -5.06 1.1 c 4 1515 82 4 29 69839:4e.18 34.2384 188.8432 -5.44 1.1 c & 1578 82 5 to 03:34s33.33 33,7813 ges,g34g -5.44 1.4 h 4 1518 82 5 3 18 42e33.34 35.83ee 1e8.93e3 -5.se .1 c 3 1577 88 5 to 33ssesa3.41 38.73?? 108,gg37 -g.se g,g g 4 1517 82 5 4 12s21st3.24 38.es34 108.e545 -5.e0 1.4 k 14 1578 82 5 as 47se7:st.Os 38.8848 108.73e8 8.3e 3.1 d 4 1518 82 5 4 15:3e:57.4e 38.70s2 105.8373 -5.0e 1.7 b e 1578 83 8 2e 07:e8:33.78 38.8549 104.7330 -5.se 11 c 4 1919 83 5 5 21101:48.22 35.8619 188.8809 -5.44 1.4 c 8 1580 82 5 20 87:378 98.78 33.38t g 138,8877 -g,ee 1,g . ?
1529 82 5 5 21113:45.14 34.4909 300.0080 -5.00 1.3 4 5 1581 88 5 88 17se8140.04 38.47 1 100.1104 -5.00 1.4 d 4 1521 82 5 5 21:27:25.78 34.5474 148.8237 -5.00 1.8 4 3 1508 82 5 It 05:51:11.84 38.83t8 108.8487 -5.00 1.3 . g 1533 83 5 8 ets53s43.71 35.8724 144.0908 -5.e0 3.0 t tg 1583 ta' 5 at 08:53:28.01 38.8834 108.1373 -3.0e g.3 , g 1523 03 5 8 els5 essa.13 30.0958 184.7e01 -8.ee 1.3 b 18 1584 83 5 It 02st?s58.Se 33.9997 108.83t8 -5.00 8.6 c 8 1524 32 5 8 33:37854.71 37.1133 107.3175 -5.00 1.3 h 4 1585 83 5 33 10:08:43.3e 38.g4g4 ges, geog .g,Ge .8 e 5 1525 83 5 7 811:4:47.01 37.1111 197.8578 -5.se 1.3 g g 1888 88 5 33 19:54s35.33 37.8338 107.310e -5.00 1.5 b 4
long depth ass quel no age date tise tot long depth seg gest no ada debe Line tot 4.0 e 4 1587 35 5 to 0e848:33.78 38.8708 108.7185 -5.88 1.3 e 8 1640 1s.g se83a3e7387:01:14.33 7s ess 39.7328.5D58 38.8447 106.8457 108.7438 -5.00
-5.04 f.2 a to a 5 1538 32 5 24 esse 3:45.83 34.8855 108.7176 -5.00 1.3 c 8 8654 32 8 9 48ettsts.79 34.70s4 804.7843 -5.44 a.8 e at 153g 38 5 34 ess3as51.84 34.4495 108.7094 -5.00 1.9 1.5 h 8 asst 82 8 It testseed.te 38.8450 108.7155 -5.04 1.8 e 8 159e sa 5 24 es s 4 3 8 52. 32 38.8748 186.78 28 -5.e4 1.4 c 4 tssa at a la 08:40e28.34 34.8810 108.8450 19.10 .3 1591 88 5 85 ess45s50.24 38.5581 108.7480 -5.se 1.8 c 5 1853 82 8 11 10:e3839.79 36.6588 108.7853 -5.04 8.8 e in 1598 32 5 25 46812e38.98 34.3788 105.3722 -5.00 .9 b 4 ts54 42 8 18 09835s58.33 34.7223 164.0425 19.44 .8 1593 82 5 25 09133e17.88 38.8442 105.8931 -5.00 .5 c 4 8555 82 8 14 18:58 08.30 35.938e 108.D505 -5.00 1.7 e 11 1594 83 5 25 tes50e42.50 35.3348 887.1880 -5.08 1.5 e a 3655 32 3 15 e383083e.75 35.3206 107.8578 -5.04 1.0 e 18 1595 32 5 25 05e59s52.78 35.6984 106.7121 -5.00 1.5 h 5 ts57 33 e is 23:e3:37.57 35.7980 104.9449 -5.00 1.8 4 3 1598 se 5 28 38:30:53.79 38.8089 106.5533 -5.00 8.5 c 5 3653 32 8 19 e1852141.75 38.4400 104.8415 -S.06 1.9 e 13 1587 88 5 28 12:49:28.9s 34.38 3 387.8843 -5.99 1.8 d 5 1959 82 8 19 058tge31.46 30.8581 108.7893 -5.04 1.3 h 8 1598 92 5 28 20830s47.35 36.3679 106.7848 -5.00 1.9 4 7 38ee 3a 8 23 ess30sts.55 34.8150 108.4817 -5.04 .9 b 7 3599 83 5 28 22:37s ts.50 36.735e 306.98e3 -5.00 1.3 e 4 s468 sa 3 24 07859838.D6 34.8751 108.8864 -5.00 1.3 a 9 1894 St 5 27 43822:42.21 38.5345 808.7730 -5.00 1.5 b 7 1882 82 8 28 17:48sts.44 35.8450 109.0005 -5.64 3.8 c 17 188 33 5 37 oge41e43.35 34.8298 186.7444 -5.00 1.3 1.1 e 8 1603 82 5 27 08:23:31.42 38.8526 105.7188 -5.00 a # 3643 Sa e i 178 488 44.1e 34.7018 108.8388 -8.44 1.2 4 9 1893 et 5 27 38:31118.84 38.5630 106.9487 -5.08 1.1 d 7 1684 02 9 3 93e37e07.84 35.9855 108.1634 -5.04 1.8 c 4 3844 82 5 27 08 e et e 47.21 36.7 377 104.821e -5.00 1.7 c 8 1665 32 9 7 07 e et e E 4.e5 38.7384 108.0414 -6.04 3.4 b 3 1805 32 5 27 tse26ste.10 36.4799 te8.7528 -5.00 1.2 b 4 SEss 38 9 34 33sa7 sal.74 35.8257 108.1535 -5.04 1.3 c 3 1604 32 5 27 15e52826.15 34.381e 105.3596 -5.08 t.S b a tas7 33 9 14 13145s35.83 35.8093 147.4714 -5.04 1.8 c 4 1647 82 5 at 02 41 14.74 35.8831 107.0898 -5.00 1.1 c 5 1663 82 9 15 18849e43.45 34.8605 148.84to -5.44 8.1 1.5 c 8 tess 82 g is 03:39:41.48 34.3808 108.8807 -5.44 b 8 1698 32 5 29 95s51884.18 34.0644 108.7006 -5.00 1.8 e 4 167e It 9 18 0314tets.87 34.3827 104.0017 -5.44 2.2 c 5 1889 82 5 20 07 24s50.57 34.5551 106.7243 -5.00 1.3 a 4 1671 88 9 28 83:55s20.10 34.0300 107.0825 -5.44 3.4 c 5 16te 82 5 29 47825:45.38 34.E642 106.7029 -5.00 1.3 5 1672 32 9 23 23 32e31.98 33.8087 144.6842 -5.06 1.4 c 12 Igit 82 5 29 e9s3es36.23 36.5495 tes.7425 -5.00 a 2.8 c 5 tsta 32 5 34 0e:07:44.0e 35.2391 106.6218 -5.00 1.3 b 5 1s73 82 9 25 21804000.94 38.8459 108.8886 -5.04 4 c 2 3813 32 5 30 03827e52.81 35.8712 108.7183 -5.00 14 a 9 1874 82 to 4 18:57s37.49 35.1440 147.3388 4.84 1.3 b 5 1814 82 5 31 19:35e30.Se 38.8991 187.0G16 -5.09 t.3 c E 3675 82 to 8 23:15:16.11 35.1566 106.3437 -5.00 h 4 1815 82 5 31 19837839.33 34.8631 106.7288 5.88 1.3 b 83 167s 82 to 7 12:4t:29.se 34.34t8 108.7774 -5.00 2.3 1.0 e 7 03 1888 82 6 2 00st9es3.04 36.6853 306.67:2 -5.00 1.3 a 9 sc77 32 to to 17:37:48.52 35.3784 107.8944 -5.06 1.3 e 6 e 1817 82 8 12 18:44852.93 36.5815 106.7302 -5.00 1.2 d 5 16?e 32 to 11 22850s54.98 34.3953 144.7940 -5.44 c 4 1818 82 8 12 18:59:18.11 35.8502 106.7138 -5.00 2.0 a 13 1679 37 to it coe44:27.el 38.9781 100.1394 -5.00 1.1 1.4 c 8
'" 1819 et 6 28 13s32:33.24 35.53:0 108.8708 -5.00 .6 c 5 isse 82 to 13 04:48s18.92 37.7988 107.9182 -5.00 d to 1420 32 8 28 08:44841.78 35.5124 107.5231 -5.00 1.0 4 4 1648 82 to 14 12851849.21 35.8231 102.5437 -5.04 3.0 lett 82 8 29 ese42st1.e3 36.7474 106.75 3 -5.00 1.8 b 5 1682 82 to 18 tsst3143.g3 34.7174 106.3391 -5.00 1.1 a 8 1.8 a 12 ass 3 82 10 21 23:29:18.84 34.9552 148.1440 -5.00 1.3 c 5 1822 82 4 28 11:43:25.8e 38.875: 108.7360 -5.00 .8 4 3 1604 82 le 24 13stte53.ta 35.4831 107.4918 -5.44 1.3 c 6 1823 sa 0 29 11:51882.71 38.7419 106.1518 -5.es .3 d 3 1685 82 to 25 86stes30.49 38.3039 188.3231 5.44 1.0 d 3 1824 82 8 29 11 51858.83 35.8185 104.2794 -5.00 1.2 d 4 16e8 32 to 27 41s05119.19 35.5885 147.3343 -5 00 1.7 b 7 1825 32 8 29 11:54e40.61 38.5000 108.8070 -5.00 1.4 e 5 1847 82 to 29 22:35s07.11 38.2878 104.8503 4.94 .5 d 3 1926 82 8 29 11:57e24.11 36.5378 185.6950 -5.00 1.2 d 4 1888 32 at a ses37s51.59 35.9408 187.9412 -5.00 18 c 5 1827 35 8 29 12 25 54.38 38.6977 108.7341 -5.00 1.5 c 7 1598 52 11 E 23e54e05.87 35.4204 106.2545 -5.04 1.2 b 4 1828 82 8 29 33s33s43.ee 38.7372 106.3379 -5.00 1800 82 11 3 49:28s30.84 34.3935 108.8281 -5.44 1.4 h 5 1829 82 8 34 05134s51.87 38.8443 106.6890 -5.00 1.4 o it c
h 4 t$st 32 31 3 17:54ett.47 35.3248 108.7304 -5.00 3.5 18 1834 83 7 2 08e19:38.04 36.862E 806.7231 -5.00 .8 1692 82 11 8 14:03:17.18 30.8287 146.8877 -5.00 1.1 c 5 1831 82 7 2 esse 243.43 36.7453 185.7552 -5.00 1.2 d 3 c
1.7 c 5 1803 32 18 8 15e37s17.39 34.6561 108.7143 -5.44 1.E 4 1832 32 7 2 13:37:49.31 38.9753 147.3314 -5.00 h ? 1894 et 11 9 63e04:33.49 30.8407 338.8883 -5.44 t.8 h 4 1 4833 58 7 4 03 19133.11 38.8400 106.4545 -5.00 2.0 1.3 1895 82 11 9 20:55s08.31 37.3848 107.3884 -5.64 1.4 4 8 l 1834 83 7 4 33113s01.88 38.2128 105.9591 4.60 1.3 4
c 3
3 1898 se it te 09:33:35.te 35.3605 107.8945 -5.00 15 d 3 1835 82 7 8 21:05:59.72 35.1935 387.20e5 -5.06 1.1 b 5 1897 33 11 33 09:33:e3.53 38.85:e 100.e383 -5.0e t.5 c 4 l 1838 SR 7 9 03:38 30.28 36.485e 106.7572 -5.00 1.8 d 3098 83 11 13 09884804.18 38.7955 108.7318 -5.08 1.8 d 5 l 1837 82 7 3 04:03e43.42 36.5e60 108.0818 -5.00 e 37 8
tese et 33 13 ess48s47.85 38.8307 338.7848 3.94 3.7 d 33 3838 38 7 18 14 37s48.29 35.5754 107.8305 -5.00 2.5 8.1 d 6 1700 33 31 13 ses57e55.08 38.1478 108.7784 -5.00 a.t b 7 1939 82 7 14 23s44150.77 35.2006 108.5575 -5.00 1.1 d 4 1701 88 11 19 ele 34st3.e3 35.8570 104.8444 -5.00 1.3 d 3 1848 SE 7 17 08:06 51.19 38.3408 108.8234 -5.08 1.3 5 1782 at it 19 10s48 58.38 35.5578 108.1803 -5.60 1.8 d 3 1841 88 7 30 tt:33s40.84 35.7437 100.9291 -5.00 3.9 b
33 1703 03 11 28 08:53 e 44.99 38.8119 100.g338 -5.00 1.8 c 8 1844 88 7 83 tas48e34.51 35.8891 188.9223 -5.00 1.1 a
d 4 1794 sa 11 as e3:01:38.34 38.7050 100.0499 -5.00 .8 d 4 1843 sa 7 22 13818853.59 35.7777 100.9847 -5.00 17e5 82 18 8 41:48e40.78 35.8854 107.0931 -5.00 4 4 3 1844 It 7 88 30:51:08.38 35.8743 106.9795 -5.00 1.8 e it 1848 88 7 33 31137:00.75 35.7308 104.8400 -5.00 .8 4 4 1700 83 it 15 14:55:00.73 38.3883 338.3371 -5.0e .9 b 3 2.7 e 13 !?e7 08 18 le 04:e3103.87 35.0048 100.9331 -5.04 .9 c 4 1848 St S 7 84s40s01.98 30.8520 100.6987 -5.00 10 c 7 1847 32 8 7 e4:55e44.52 35.E448 tes.7263 -5.00 1.4 h 4 t?ss sa la II e1:31:43.00 35.3931 105.3840 -5.00 l
I i
I ada date ties tot tems depth ees qual na Ida date Lise let long depth seg ' quel as 1709 SI 12 23 23s07:58.30 34.9838 108.8315 -5.00 .9 d 3 177e 83 3 18 18:14:35.78 35.4865 100.0789 -5.00 1.0 4 4 1710 88 la 22 23:e0:58.94 35.41e8 185.2706 -5.00 1.9 c E 1773 83 3 18 ed e28e 45.83 38.0844 148.8197 -5.00 .8 b 8 1711 S4 12 24 19888s45.26 35.1736 146.8949 -5.00 1.4 d 5 1772 83 3 15 00s87s03.37 34.3548 108.7418 -8.00 1.8 c 7 1712 82 12 3e e2:24:12.38 14.5884 106.7140 -5.e0 1.8 4 3 1773 83 3 18 98:38:15.43 34.3068 107.4448 -5.04 8.4 d 4 1783 83 1 1 15:15:39.18 35.7718 136.8947 -5.00 .2 c 4 1774 83 3 IS ess30s31.30 34.3357 104.8544 -5.00 1.2 e 4 1784 83 1 8 80s44s53.98 36.7458 885.70t8 -5.00 1.8 d a 1775 83 3 17 18:04s51.83 37.8138 104.8867 -5.00 1.8 d 5 1715 43 1 6 22:43s03.72 35.4182 188.1414 -5.00 3.4 c 7 I??S 83 3 17 42s35154.88 34.1533 104.8384 -5.04 3.8 c 7 37 6 83 1 8 01:30 12.98 36.8299 106.8956 -5.64 1.1 b $ t??? 83 3 at ecst5ste.48 36.3801 147.3708 5.00 1.8 c ?
1737 83 la 18s3t:13.25 34.3304 805.2109 -5.e0 1.5 b 13 1778 83 3 23 41800:34.08 34.3105 104.7413 -5.04 1.1 b 4 1718 83 1 12 14s50s39.78 35.4513 106.7372 -5.00 1.7 e 12 1779 43 3 31 86stese8.64 34.8548 108.48 3 -5.04 1.8 d 4 1719 83 1 13 20:45s2e.68 37.2440 104.4854 -5.00 8.9 4 6 170s 83 3 31 88 42854.84 34.8348 104.8791 -5.00 1.5 c 4 1720 33 3 14 ese40sts.88 35.1413 107.2668 -5.00 1.4 d 5 1701 83 4 8 88813st8.81 35.4400 188.1894 -5.06 1.3 c 5 1721 83 8 14 13:4te37.08 36.A498 106.7985 -5.e4 .8 d 5 1782 83 4 5 17 40s35.88 38.0512 108.8433 -5.04 .8 c 5 1722 83 1 14 15835e58.04 36.50t8 108.8531 -5.00 .6 c 4 1783 83 4 8 tes30s48.38 38.1548 108.3400 -5.04 .5 b 8 8723 83 3 14 19:e5 18.23 35.8545 107.8788 -5 06 1.5 d 5 1784 83 4 4 11845e25.81 35.3710 107.0888 -5.99 .3 c 3 1724 83 1 15 09:24s05.50 35.3981 107.4832 'S-re .7 d 4 1785 83 4 9 03:58:14.81 34.3741 105.3745 -8.64 1.3 4 5 1725 83 1 15 15 38 58.82 35.7320 188.7500 -5.pe .8 d 4 3788 $3 4 14 13st3s54.Se 34.3444 104.9574 -5.00 1.5 c 4 1728 83 1 18 15:47 42.70 35.3634 104.3869 -5.00 1.4 d 5 -
1787 83 4 18 48s17:59.54 34.l?!1 108.1278 -5.04 .5 4 5 1727 83 1 23 22:39:07.78 35.2728 107.1281 -5.0e 4 4 4 1788 83 4 17 04 04s58.73 35.4885 107.3333 -5.00 .9 b to 1728 83 1 25 esselst4.34 37.9899 104.1119 -5.00 1.4 d 5 1789 83 4 17 11:34:27.43 34.1775 104.7245 -5.44 1.3 d 3 1729 83 1 25 e5stestl.25 35.9318 106.7726 5.00 .5 b 3 1790 83 4 28 18:20s33.88 34.2320 148.8773 -5.04 ,r.3 c 4 1734 83 1 27 11:e8s24.12 35.2995 167.5332 -5.00 .8 d 3 1798 83 4 25 08s05:18.8% 34.7289 106.1320 -5.00 1.0 h 8
, 1731 83 1 29 05:17:34.06 36.73tG 106.7468 -5.00 1.5 c 7 1782 83 4 28 17:34s28.04 34.2824 108.8942 -5.08 8.2 e 5 1732 83 1 31 12:40s21.05 35.5789 107.2584 -5.00 2.8 b 12 1793 83 4 28 18:29sta.84 37.3240 107.3889 -5.44 1.2 d e i 8733 83 3 1 43s54851.97 36.5887 106.6079 -5.00 1.4 d 6 1794 83 5 4 03:15:1e.0e 35.3987 107.3199 -E.00 4 e 7 1734 83 2 4 15:50e29.43 35.1678 107.1737 -5.00 1.2 d 4 1795 83 5 6 09:32:54.te 35.4838 107.3247 -5.04 .8 c 5 1735 53 2 4 10st4s39.51 35.9110 108.1993 -5.55 1.4 h 6 1796 83 5 7 22:50s38.38 38.9699 185.2819 -5.08 1.5 d 5 l 1736 83 2 11 e4819:28.15 35.9171 106.7855 5.00 .5 h 6 1797 83 5 to 00:38s55.11 34.0754 105.9135 -5.00 3.3 c 5 1737 83 2 15 19:51s55.13 35.4589 105.7676 -5.00 .3 d 5 1790 83 5 20 15:51807.04 35.8704 108.8466 2.40 .9 d 5 C8
- 1738 83 2 19 17sess34.77 38.6183 106.5822 -5.00 .5 c 5 1799 83 5 24 17e51s34.84 34.9575 105.8252 -5.00 1.5 d 7
_o 1739 83 2 19 17:15146.22 36.G951 185.7243 -5.04 1.1 4 6 8800 83 5 28 17s t7e 58.89 36.6240 165.3184 -5.44 2.5 d 7 1
an !?te 83 2 24 21:23:5E.31 35.1116 106.7001 -5.00 1.6 c 4 1801 83 5 28 17:31:31.12 36.9884 184.1981 -5.00 1.8 d 6 1741 83 2 25 02:57s53.35 34.3583 106.8441 -5.00 2.1 c 5 1842 83 5 28 18:34e19.84 37.1848 184.1778 -5.00 2.2 d 8 1742 83 3 25 08:49:58.57 34.3a37 106.8870 -5.00 1.3 c 5 1883 83 5 27 24105s34.33 35.8781 107.0734 -5.00 e.e d 4 1743 83 2 25 15:32s09.50 35.4428 147.3515 4.00 1.7 c 7 1884 83 5 27 22:29145.75 37.3025 344.4394 -5.00 1.3 d 8 l 1744 83 2 28 98 s 42 s t 4. 46 34.5858 107. 3108 -5.48 1.5 c s 1985 83 8 11 18:e1857.75 35.5837 105.5340 -5.00 .8 d 4 j 1745 83 2 28 t i e t s s 39.75 34.14 2 105.8554 -5.08 2.8 4 8 1888 83 8 8e e9else03.03 34.8252 105.7854 -5.04 .6 c 3
- 1748 83 2 28 04s52
- 20.47 36.8899 106.2268 -5.00 1.1 e 4 18e7 83 8 24 88828152.29 38.4003 148.8295 -5.04 .4 b 5 1747 83 2 28 23:12:39.74 34.1329 106.1717 -5.00 1.7 c 5 1808 83 8 27 Stette64.45 38.3464 104.8735 -5.00 .8 c 8
!?ts 83 3 3 18 s t 4 s 38.00 34.4345 107.9592 -5. 04 1.4 d 4 1889 83 8 30 65812818.78 38.4589 104.7487 -5.04 1.5 h 7 1749 83 3 2 20:4t:22.93 35.1273 104.7844 -5.00 1.4 c 3 I8te 83 7 2 00:07 58.78 35.0740 108.1768 -5.00 1.1 c 8
! 1750 83 3 2 23:22 10.?? 34.3e36 348.8703 9.8e 4.2 e 15 1881 83 7 5 17e55sel.13 35.4000 107.3892 -5.00 .9 e 9 175 83 3 3 23 8 47 34.45 34.3198 107.e518 -5.00 e.e c 4 1912 03 7 5 18:59:48.43 34.1725 108.1845 -5.84 1.4 c 3 1752 83 3 2 23s48s38.88 34.3778 108.7965 -5.00 1.3 c 3 1913 83 7 8 ele 41:57.05 35.5965 107.2553 -5.00 .5 e 8 1753 83 3 2 23s40844.88 34.2387 148.7747 -5.00 1.0 d 5 1814 83 7 8 88148808.83 35.5185 107.3828 -5.00 .1 4 4 I
1754 83 3 2 33sles35.88 34.2871 108.8395 -5.0e 2.0 d 8 1815 83 7 8 09:49:15.08 35.9435 108.3818 8.30 .1 e 5 1755 83 3 3 ess32s48.47 34.30es 135.8200 -6.00 1.3 4 4 1818 83 7 8 14sats37.e4 38.4403 107.3e88 -5.00 11 b 8 1758 83 3 3 42:08 34.01 34.3057 146.8447 -5.00 1.8 4 8 1817 83 7 8 21:11:41.88 37.3338 107.3403 -5.00 t.t c 4
) 1757 83 3 3 titles!7.28 34.5304 108.8254 -5.00 1.4 d 4 1818 83 7 18 23:08 14.38 34.1133 30s 9338 -5.se 1.3 c 5 j 1758 83 3 3 17 8 40 s t 2.90 3 4.3048 106.9620 -5.00 3.4 c 8 3839 83 7 18 15 03:33.3e 34.9431 104.8888 -5.00 .8 d 8 i 1758 83 3 3 18:12:34.48 35.8438 100.3551 -5.00 3.0 d 5 1820 83 7 18 17:13:43.33 38.3848 108.8350 -5.44 1.1 4 4 4
1788 83 3 4 essess21.52 34.1943 188.70e8 -5.00 1.5 c 5 1821 83 7 29 19111854.24 34.2980 105.8828 -5.00 8.7 b to 1741 83 3 4 fis47s57.31 34.3445 108.87e3 5.10 1.2 d 5 1822 83 7 21 04s17:00.28 35.3937 337.3383 5.00 7 h 3
, 1782 83 3 4 e5:28 s te.95 34.2623 1e5.8083 -5.00 1.5 c 5 1823 83 7 41 19140 s 38.03 34.7878 te4.7534 -5.00 1.1 d 8 1783 83 3 8 80s34:57.00 34.3218 185.9485 -5.00 t.s d 4 1824 83 7 34 test 4ste.75 38.0388 108.9408 -5.00 1.0 e 7 1784 83 3 8 98:35 0s.45 34.2578 106.8123 -5.00 1.8 s 5 1825 83 7 28 15 58e87.St 35.4037 148.1988 -5.00 1.3 b 8 1785 83 3 8 ess27e39.54 34.2175 108.7531 -5.00 1.1 c 4 1820 83 7 08 13:58s48.28 33.9879 108.78e5 -5.40 18 c e 1788 83 3 0 00:05 57.19 34.1498 108.8709 -5.00 t.4 e 3 1827 83 0 1 47:39:40.41 30.3338 105.7334 -5.00 .7 c 8 1787 83 3 9 33:24:34.81 34.3734 geg,774e .5.00 1.8 c 5 1888 83 8 3 e8:17:33.48 30.0843 te6.Bles 4.ge 3.1 b 8 1788 83 3 11 44s04:15.57 38.8934 108.7488 -5.00 1.8 c 8 1929 83 0 3 10:05:33.51 35.8847 107.3489 -5.00 .5 d 4 i 1789 83 3 11 83sI4 35.8s 37.43es 187.8635 -5.00 1.5 c 8 .1834 83 8 3 17:09 37.48 35.3455 144.7192 -5.00 1.5 d 8 l
, t I
i i
ida date stee tot less depth' eag gaat me Idn date Llos 1e5 l*ng depth' oog gaat as 1931 83 8 9 00:38s08.34 35.0868 tes,8138 -5.04 1.9 c 3 test e4 4 15 tes50sta.15 35.4404 147.3144 -5.00 1.4 6 e 5 4
1832 83 8 9 19:39ses.17 34.9682 104.4094 -5.84 1.3 d 4 1893 84 4 to 19:44:04.34 35.9511 104.8717 .00 1.8 d 3 1.9 b 9 1894 34 4 18 Sts00stg.38 35.3709 847.4184 -8.04 t.8 ts)3 33 8 11 15s09:23.49 38.3434 195.Se56 -5.se 1.3 b 7 1895 54 4 84 14:13s08.75 35.8743 106.7878 3.04 .8 b 3 1834 e3 2 14 14:45s02.51 35.1952 106.4541 9.18 b 1s35 33 6 23 00:24s44.37 35.7459 105.9946 -5.00 .3 b 4 1896 84 4 as 14s17:43.83 35.0400 104.7438 4.64 .9 b 3 3
1836 33 8 31 18812:58.98 35.8308 107.3148 -5.00 .6 e 5 tag? e4 4ft ess43sSt.95 30.0338 105.4818 -5.00 .9 1837 33 9 2 19s53:06.72 34.2078 105.2730 -5.00 1.1 c 4 tage 34 4 44 87:43st5.77 35.9858 104.8540 3.44 1.0 e 5 1838 33 9 12 00:52847.78 35.4971 107.4881 -5.30 1.5 h 4 tage 34 4 24 33s15:34.85 38.9583 105.3834 -5.04 18 d 3 8839 33 9 15 eest2s59.33 35.4627 te7.6875 -5.00 1.8 b 4 1940 84 5 5 00:33 34.85 34.8173 108.8834 -5.00 1.8 c 8 .
test 34 5 8 84s47s59.45 35.0718 198.8904 -5.09 .8 h 3 184e 33 9 15 23:25s37.34 35.8700 194.4900 e.e3 3.2 i 1848 33 9 18 12sesse4.31 35.2543 108.1927 -5.Se .9 e 4 test se 5 8 40stis38.13 35.4558 187.t??t -0.04 .8 b 5 7
1982 33 9 15 05:08:07.81 35.7438 106.1003 -5.00 .7 h 4 8983 34 5 8 87s3es59.85 34.8874 104.4483 -5.04 8.7 1.5 h
h 3s43 33 5 23 22:51st4.58 35.3149 804.5859 -5.00 .9 d 4 - 3904 34 5 18 17:39:54.33 34.1488 105.5585 -5.44 3 1844 03 9 23 23:59:44.87 35.4488 147.8060 -5.00 1.9 e 7 8905 54 5 18 38:45s13.32 35.3784 148.835s -5.44 1.4 c 5 ,
1945 33 9 25 07sl8 41.40 35.4358 107.8341 -5.48 .3 e 4 19es 84 5 le 18888s18.83 34.3485 106.5988 -5.04 3.4 c 5 1845 83 9 25 17:30s55.18 37.121t 107.3948 -5.00 .9 b 4 19e7 84 5 38 18 55s13.81 35.33 5 187.8348 -5.44 1.1 d 4 1847 33 9 29 47s44ste.97 35.13E5 104.4991 -5.00 2.5 c 8 I9es 34 5 24 19:33:03.10 34.4048 104.4948 -S.49 1.9 a e teve 33 18 3 04:54s53.54 34.8319 106.4932 -5.48 .7 b 4 19eg 34 4 4 e2:54s18.71 38.8838 108.4548 -5.04 8.9 b d
! 7 19:18s19.05 35.8432 108.1795 -5.00 1.5 h 7 tote 84 4 5 03:45:04.27 34.7941 104.4736 -5.04 1.1 b 8 1 tia g59g 33i 3 t o. 9 ee 59:5s.53 35.50s ie7.3se -5. e .9 b s 19 s4 8 8 e4:55s55.t5 35.ses3 3e8.1:35 -5.ee .8 h 3 1851 53 le 9 22:47s44.4J 38.1877 tes.sett -5.00 1.7 b 5 39 2 34 t 9 21:10:14.18 37.1328 107.4220 -E.00 1.5 c 4
'l' i 52 s3 le 17 23:5ss53.51 1s.4453 te5.5e54 -5.ee 1.s c 8 19 3 si 8 9 at:34ste.et 37.1883 te?.8733 -5.ee 1.5 d 4 1853 83 le 23 17s5t:33.st 35.2E94 105.7793 -5.00 .5 d 3 1914 34 8 le 05:17s57.53 34.1359 168.7863 -E.00 1.4 c 5 l 1854 33 te 23 tes36s35.50 36.2650 te6.2e72 -5.00 .5 a 3 1915 34 8 le 80s40s48.59 35.4283 107.5444 -5.00 1.7 c 7 j 8355 83 to 23 12 41s48.44 35.4e78 te7.4393 -5.00 2.4 c 5 1918 34 8 25 03 48s00.52 34.1782 te6.7199 -5.40 1.4 b 5 i 1858 83 le 29 e3:57st2.41 35.8794 106.5131 2.50 1.4 e 18 1917 84 8 as 01st3:34.33 34.3951 106.0692 -5.00 1.3 h 5 1857 33 10 31 lis4Ss54.47 35.4213 107.4274 -5.00 .9 e 4 tels 84 6 34 12:02 53.34 38.5638 106.1982 -5.48 1.3 a 8 8858 53 le 31 17se2837.09 3G.9834 105.7778 -5.90 1.8 b 4 1919 84 7 7 20:58 e5.74 36.3296 106.5551 -5.ee .5 c 3 en 1859 83 11 8 47s53:53.45 34.3399 te5.7533 .5e 1.4 h 5 1920 84 7 8 07:4Eset.41 36.5200 105.2431 -5.te .5 b 3 s 1860 83 11 8 14:24s46.03 35.4968 107.4151 -5.00 1.0 d 3 19a8 se 7 9 19st2:32.71 35.44ts 145.5427 -5.08 f.e b 3
-d test 83 11 to tes24:47.59 36.3e46 105.8824 9.30 .7 b 4 1922 84 7 11 47s45:15.50 38.3453 168.8352 -5.44 .3 b. 4 i
'd 1862 33 11 11 17:32s39.35 35.4137 147.4132 -5.40 .5 a 3 1923 84 7 12 00s53814.72 34.5433 105.9998 -5.00 1.0 h 6 i 1983 83 11 18 t e s t 5 s 27.47 35.2254 106.834e -5. ee t.1 d 8 1924 34 7 15 07:14:44.36 36.5516 146.6182 -5.e8 1.3 b . 7
{ 1864 83 11 23 00s38sta.01 34.4901 106.05t4 -5.00 1.1 b 3 1925 54 7 15 07:35 11.58 38.8843 1 8.8534 -5.40 1.4 b 7
! 1865 83 11 25 17:25see.34 34.4973 144.4384 -5.00 .9 b 3 1928 84 7 to 22 s 55194.50 35.5811 187.3291 -E.44 .8 c 4 l 1865 33 11 28 17:3t:33.10 38.4997 105.9747 -5.00 1.3 e 5 1927 84 7 18 18:18:20.93 30.2410 180.0523 -5.00 .5 h 4 1867 53 12 2 22:09 59.47 36.1960 1s6.54e2 -5.00 .8 h 4 1928 84 7 10 05:14:18.81 34.8384 148.8571 -5.ee 1.4 c 4 1888 33 12 2 22s44ses.87 35.2111 106.5435 -5.40 1.2 h E 1929 84 7 19 tes50ste.87 38.9895 168.8807 -5.64 .8 e 4 1866 33 12 4 42sess54.se 36.8tE2 188.5704 -5.00 1.4 h 5 1934 84 7 2e 18:14:49.58 30.4245 104.7988 -5.00 1.3 d 4 1874 83 13 19 10:57 s 52.25 36.8718 106.58 05 -5.co 1.4 c 6 1931 84 7 20 34stes54.35 38.4147 104.7874 -5.00 1.3 c 5 1871 83 12 to 11:08:28.18 34.5ete 104.0731 -5.00 11 c 5 telt 84 7 at 23 s E7:30.30 35.4325 105.5493 -5.44 1.3 c 5 1872 83 18 28 94s5Gs15.3E 36.3159 te5.78te 9.30 .7 b 3 1933 84 7 20 83s43s04.15 30.8785 108.474e -5.40 1.1 b 8 te73 04 1 4 15s3t:51.)2 34.4040 105.9645 -5.00 .9 h 3 1934 84 7 22 03:07 57.17 34.4901 108.7454 -5.00 1.1 b 4 1874 94 1 11 9s33821.78 34.5397 105.9309 -5.00 1.8 b 2 1935 84 7 27 19stasta.Se 38.1918 106.9179 -5.00 1.0 s 5 1875 84 1 23 14 40s33.34 35.8045 107.2762 -5.00 1.4 c 5 1938 04 7 30 12:40 set.75 34.7847 106.9530 -5.0 1.1 e il 1878 84 1 27 44:52:26.93 35.8419 107.9519 -5.00 1.1 4 3 1937 84 7 29 18:35:18.88 38.3500 107.3530 -5.e0 1.8 c 8 1:77 se t 28 2es45sai.47 38.44s2 to?. stet -5.se a.: d 4 193: 84 : : 23 Sas5s.e4 35.8845 toe. tees -s.ee t.5 4 3 1878 s4 29 e4sassta.14 35.eee4 tes.75 3 -5.ee .8 h 5 193s e4 8 12 ses43se3.13 35.34t5 t 5.43ee -5.se .7 4 3
- 1879 84 t e 2.8 4 5 1948 84 8 12 ess50s35.58 34.4920 108.0743 -5.00 .3 c 3 isie 84 e '3 19:58 3s44 set.38 s 59.5735.1754 34.5837i. t #8..e415 0992 5.e-5.00 4 1.8 . iO4s 4 8 is iis32:34.ii 25.705. see.. Sit -5. e . t 5 1881 84 3 4 11:10:28.54 36.4153 te5.3tet -5. e 1.1 b 5 1943 04 8 38 42:19 58.00 34.3684 148.7984 -5.04 8.8 c 8 1882 St E 5 esse 5:25.Ge 35.9340 106.5855 2.50 1.8 h 4 1943 84 9 28 e5:38s45.08 34.3583 100.1378 -5.00 .9 h 4 1883 84 2 14 13sses40.St 35.4851 104.880J -5.ee 1.4 h 4 1944 84 9 24 81s33:38.0s 38.8418 144.8334 -s.4e 1.4 h 7 1884 54 8 39 31:59s44.73 35.4557 167.3635 -5.00 .5 4 3 1945 84 6 37 e4sesset.18 34.0703 188.0883 -0.00 1.7 h 9 1985 84 3 1 22s23:38.70 38.1458 let.0934 -5.ee 1.8 d 5 1948 04 8 30 fas4ese1.18 35.3311 105.0478 -5.00 1.5 d 4 i 1850 84 3 4 18s33:10.49 34.3337 146.3942 -5.00 1.0 d 2 1847 84 9 3e e7s30s20.85 36.7835 103.9403 -5.ee 1.7 d 4 1887 84 3 15 13:58s48.75 35.1818 tet.It47 -5.ee .0 d 3 1948 84 to 13 31 04:39.07 35.7589 104.4393 -5.00 1.3 e 5 ISIS 84 3 19 23s45:19.91 37.1988 107.3871 -5.ee 1.3 c 5 1849 84 le 39 23:40 24.80 35.8819 148.4835 -5.00 1.0 d 3 1533 84 3 20 00:43ste.53 35.9831 107.8821 -5.00 s.4 d 3 1958 84 11 5 00848:05.14 39.See5 100.e450 -5.00 1.8 c 4 189 84 3 34 31:188t4.88 38.174e tet.7355 -5.ee .0 d 4 1981 84 11 5 13:00:18.57 34.3831 104.3838 -3.e4 1.5 c 5 1881 84 4 11 03:14s30.08 35.4180 107.3e43 5.0. 1.7 h 5 telt 84 11 0 07s40838.88 35.3814 187.3370 -E.44 .7 b 18 l
1
i .
i ada date Llee tot long septh nog quel no 1953 54 11 ? 03881:44.38 34.1948 194.8804 -5.00 4 b 3 itse 84 !! 10 Ste37st3.03 35.3450 107.8504 -5.84 1.4 h 5 1955 84 !! 13 08:30s98.93 38.5501 106.7100 -5.04 7 d 3
.9 e 4 1958 84 11 IS 14:14:13.48 35.3040 106.4144 -5.09 1.1 b 5 1957 Se it at 80s48:34.10 35.7085 106.4222 3.50 h 5 1958 54 11 at 81:21848.38 35.7828 888.4883 7.40 .8
.6 c 4 1559 84 11 Et 03:28s51.17 35.3111 107.2833 -5.00 1.1 c 4 1984 84 11 ft 23:13:44.87 36.6412 105.6538 -5.00 1.3 c 3 1981 84 11 as 33845854.89 34.5820 185.3297 -5.00 1.s d 3 1962 54 13 3 28809:54.72 35.8813 100.9656 -5.06 8 h 4
' 1963 34 13 10 99:07 58.43 35.7601 105.4214 S.50 1.2 4 8 1954 84 la tt 09:53838.84 38.1548 107.7530 -5.00 1.5 c 4
! 1985 84 la Et it:30s50.te 35.5684 107.9824 -5.00 1.5 c 5 1984 34 la 28 09:25s35.39 35.5264 107.9629 -5.00 1.4 c 4 1967 54 12 22 13s37s47.39 35.0349 107.5834 -5.94 9 b 4 1980 84 la 32 20s56:17.95 35.5452 100.0021 -5.00 1.8 h 4 1989 84 12 83 92stss57.et 35.5548 198.0019 -5.00 .3 c 3 1970 84 it 23 te s ta s 57.68 35.50 49 107.8708 -5.08 .8 b 3 1971 84 13 23 17s37:44.31 35.5426 108.0117 -5.40 .9 c 5 1972 34 12 25 12:57:14.78 35.8737 107.3548 -5.00 1.0 d 5 1973 84 12 25 14:29 38.90 36.570s 104.5672 -5.00 1.3 b 3 1974 54 12 29 42:22:52.19 26.8853 148.9870 -5.00 Letet me. of epicentere a 1974 end of diosple 8.2 -- 19432 vectore generated in 1 plot frenes.
-seeco- 4tB6 serrente vettog blvd.,sen diese celtf. 93121
- co e dieepte is a confidentist proprinterg predect of tesco end its use
{g to enbject to e mondtessesmetten and nondtectesere agressant.
- - _ _ _- - .-