Text

Submits Response to Request for Addl Info Re Use of Triga 12 W% Fuel at USGS Triga Facility
	ML20080Q629
Person / Time
Site:	U.S. Geological Survey
Issue date:	02/23/1995
From:	Hedge C; INTERIOR, DEPT. OF, GEOLOGICAL SURVEY
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9503080435
	Download: ML20080Q629 (45)
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s United States Department of the Interior l?

15 GEOLOGICAL SURVEY llOX 25046 M.S' @3 DENVER FEDERAL CENTER DENVER. COLORADO 80225 -

inmi nm,,

February 23, 1995

! Document Control Desk.

U.S. Nuclear Regulatory Commission Washington, D.C.

20555.

Re: USGS TRIGA Reactor Facility Docket No. 50-274, License R-113 Gentlemen:

This letter'is in response to your request for additional information: dated March 11, 1994, concerning the use of.TRIGA 12 w% fuel at the USGS TRIGA facility.

Since our initial application, we have found new information and acquired new analytical methods for evaluating the safety'of using 12'w% fuel.

Informal information from analyses performed by the McClellan Air Force Base TRIGA facility and the Penn State TRIGA facility indicate that the best parameter to use for ensuring safe fuel operation may be the maximum power production in the individual elements.

Although the DNB limit is quite high '(54 kW per element), operating data at other facilities indicates that a more conservative limit of 23 kW is needed'to prevent long-term swelling of the fuel clad.

Based on this data, and our new ability to calculate the power production for each fuel element, we propose to limit the calculated power production in all fuel elements to no more than 22 kW per element.

The information in the following pages is~ referenced to the numbered questions in your March 11 letter.

If you have any questions concerning this information, please contact Tim DeBey, the Reactor Supervisor, at (303) 236-4726.

Sincerely,

& f h&/

Re tor ministrator Subscribed and sworn to before me this #3& day of February 1995.

Copiw to:

@M L.J.

?.allan, USNRC, Region IV nu Tim DeBey, MS 974 Motary Public "v

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11.. Our-basis for'the statement that the onset o'f film boiling.

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is reached at.a' power density of 43 kW per element was-verbally-

received from General' Atomics personnel. -Further investigation shows that.this~ number'is conservative.

The. Safety Analysis Report for the GA Torrey Pines TRIGA Mk IIF states that a DNB f

~ ratio--of 1 is achieved at a power density.of-54'kW per element (2700 kW / 100, elements X 2.0 peaking factor).

(Ref: GA 9064.

p.3-45) 2.

Radial peaking factors were calculated in 12 w%-TRIGA fuel by GA in'1970.

This' evaluation showed that. peaking was. worst l

with a small core made entirely of 12 w%~ fuel.

.A 45 element I

core (insufficient excess to.be usable)-gave a peaking factor of 1.40 with fuel in the central thimble.

-A water-filled central thimble would increase the peaking factor in the adjacent'B-ring

{

elements by about 6.3%, giving a maximum radial peaking ~ factor of 1.49.

GA 9064, p 3-57, gives an. axial peaking factor of 1.25 1

for all TRIGA. fuel elements.

These factors apply only-to a core I

of 12 w% elements, with the elements all having no burnup.

l i

3.

The 60 element core of new 12 w% elements was an estimated operating core size..An MCNP evaluation was performed of a core

-i having 59 elements ( 56 new 12 w% elements and'3 standard fueled

]

follower control' rods (FFCR)).

This case is with the B,-C, D,

and E rings fueled and the F and G rings water-filled. 'The j

analysis shows the element with the peak power production is in l

position B-2, with.a radial peak of 1.519, giving a peak power j

of 26.1-kW in that element.

This is above our-proposed limit of I

22 kW, thus we could not use this core configuration.

l 4 ~.

The increase in the fuel temperature is conservatively assumed to be directly proportional to the power density l

increase.

Assuming an ambient temperature of 25 C and-a fuel -

temperature in an 8.5 wt element of 465 C, a delta T of 440 L

exists.

Given a power increase of 35% in a 12 w% element, the I

resulting fuel temperature is (440*1.35) + 25 = 619 C.

Recent I

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McNP analysesishow that a. maximum peak of 15.3 kW per element is possible by adding a new 8.5 w% element to the B-ring of our

existing. core.

Using our' proposed limit of-22 kW per element

for a new 12 w% element represents a power increase of about 44%

finstead of 35%.

In addition,-the reduced prompt negative temperature coefficient would give an additional 17.6% increase.

(see item 6c).

This gives a maximum pulsing fuel temperature of (440*1.44*1.'176) + 25 = 770 C.

This is below the 800.C limit in the GSTR technical specifications.

5.

As in item 4, the fuel temperature change is directly proportional to the power density increase.

The 35% power increase gives a temperature of (300*1.35) + 25 = 430 C.

However, recent GSTR operating data showed that a new 8.5 w%

-element in the B-ring operated at 15.3 kW with a fuel temperature (delta T) of 455 C.

The average power for B-ring fuel elements is 13.5 kW.

An element operating at 22 kW would then have a fuel temperature of (455*1.44) + 25 = 680 C.

After-250 MWh of operation, the new 8.5 wt% element had built up enough long-lived fission product poisons to drop the fuel temperature (delta T) to 360 C.

The temperature has stabilized at this level.

Therefore, the 680 C temperature for the new 12 w% element would be temporary and would be' expected to drop to a level of (360 *1.44) + 25 = 543 C over several hundred MWh of operation.

In any case, the temperatures are well below the 800 C limit of the GSTR technical specifications.

6a.

The fuel element geometries, dimensions and heat transfer characteristics are identical for the 8.5 w% and 12 w%

elements.

The instrumented 12 w% elements have thermocouples that'are identical in type and placement as the 8.5 w%

elements.

The maximum power generation (and maximum fuel temperature) may not occur in an instrumented element.

The maximum temperatures given in items 4 and 5 are based on limiting the element power production to 22 kW.

This is the most limiting condition.

Temperatures in the FFCR will be lower 3

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than-similar: fuel elements because the FFCR are smaller in-jdiameter, contain;1ess. uranium and'are seldom fully, withdrawn-L

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into'the active core region.

In any case, the FFCR. temperatures a'

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will';nottexceed'the maximum temperatures givenuin items 41 and:5..

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' 6b. : The.. temperature: displayed lfrom the. instrumented element:

will not be the peak core fuel temperature in most casesTsince-

' the peak. power-producing ' fuel ; element will typically ~ not be: the 4

1

'i cinstrumente'd elemente This would be due to the instrumented f

2 element having a higher burnup, higher. fission product poison 1

concentration or less power peaking due to the loading.

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a 6

configuration.

In a typical mixed core configuration, a 12 w%.

j element in the B or C. ring could be producing.approximately,35%.

I more power than a 8.5 w% element in the:B or C ring. -Our'

. technical l specifications require measuring the temperature ~in a f

B oric ringfelement for pulsing operations and'we would use a 12 1

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wt instrumented element for any pulsing-operations involving.a 2

mixed" core configuration.

JBy limiting the power peaking.to;22' 1

kW per. element, the maximum fuel temperatures achieved will bs as discussed in items 4 and 5, regardless of=whether the element-is' instrumented or not.

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6c. ~The prompt negative; temperature coefficient'for 8.5 w% fuel ^

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I is given as.10 x 10-5 and'about 55% of that coefficient isL l

from the " cell effect".

The " cell effect" of the 12 w% fuel is i

about 75% of that of the 8.5~w% fuel.

This'gives'a.12 w%

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coefficient of (0.75*5.5 x 10-5) + 4.5 x 10-5

8.5"x

'l 10 (GA 7882)

Thus the prompt negative' temperature j

-5 icoefficient for 12 wt fuel-is 85% of the coefficient.forithe 8.5:

w%-fuel.

This wouid require an increase of 17.6% in the~ element g-

. fuel temperature to give.the same reactivity feedback.

This factor is' limiting (assumes all 12 w% core) and'was included in item 4.

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6dh ; Proposed changes to GSTR. Technical) Specification ~

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The core;sha117be.an' assembly ~of[TRIGAistainless. steel s

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. clad fuelamoderator elements,fnominally>8.5 to 12'wt x

f uraniumJ arranged"inta close-packed array except for7(1).

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.. replacement <of single' individual ~ elements..with incore, 2

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irradiation facilities or,'controlL rods;n (2) ; two l

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separated experiment. positions Jin the D.. through E rings,:

f' each occupying'a maximum'of three" fuel' element.

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positions. -The reflector (excluding l experiments;and:

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experimental facilities).shall be. water or.a combination -

'ofigraphite and water.

The reactor shall not.be-operated-in any manner that would~cause~any fuel ~ element I

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to produce a calculated steady state." power, level in s

H excess of-22 kW.

D.

3.

Fuel' temperatures near the core midplane.in either the B' or C ring of elements'shall be continuously-recorded

.during the pulse mode'of operation.using a standard thermocouple element.

The thermocouple element'shall be

~i 1

of 12;wt% uranium loading if any.12 wt% loadedtelements exist in the core..-The reactor shall not'be., operated in' La manner which:could cause the measured fuel? temperature-1 0

to exceed 800 C.

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- 7.

The. table of fission product gases has been amended.

j according to"new information'.

'According to GA-9064.(Mk'III>

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SAR), only gaseous fission-products that.are in'the: space c

- between the fuel and cladding will be' released.in'the event of1a fuel clad failure.

It'also states that the bromine and iodine isotopes will remain dissolved.in the reactor tank water foriall'

. )

i t i practical purposes, and:less.than 10.%.of fissionprodue; 7sses.

with half lives <-1= minute will escape from'the reactor pool..

O These isotopes have been omitted from the analyses of airborne V

acitivities.

This results in only the krypton and xenon isotopes with half-lives > 1 minute giving significant-4l contributions to radiation exposure from the reactor room air I

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foll6 wing a claddingffailure.- The table below assumes a 100-

?['~ ^ element} core,.a'121w%ielement producing 22 kW,la' release" fraction-of 3.146'xfl0~4 and-a reactor room' volume of13.'48 x ~ J 108:m1. - The reactor ' room concentrationEis 'inimicrocuriesqper. ~al.

The : isotopes listed are # the - same~ as thoseL given in the. GA L

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J isafety analysis: forithe TRIGA Mk III.-(Ref::GA-9064).

1 _4 GASEOUS FISSION PRODUCT RELEASE 4 o Fission Activity.; (Ci) 1 in ' Reactor-1 1 ~ Yield % Half-life Core 12 w% fuel room' conc j Isotope r ' ' Kr-83m-0.544-1.86 h 4560 100 9.0 e-5 Kr-85m 1.01 4.48 h 8460 '186-1.71e-4 1 Kr-85 0.054 10.5 .y 460 10-9.0(e-6 ] Kr-87 2.76 76 min 23120 509-4.6 e-4 Kr-88 4.38 2.84 h 36700 807 7.3 e-4 'i Kr 5.47 3.15 min' 45830 1010;

9. lye-4 j

Xe-131m 0.03 12.0 d 250'

5. 5:

5.0 e-6 g; Xe-133m .0.16 2.19 d 1340 29' '2.6'e-5. 'i Xe-133 -6.62 5.25.d 55400 1220 1.1 e-3; Xe-135m 1.83 15.3. min -15330 3371 3.0~e-4 i Xe-135 6.3 9.09 h: 52780 1160

1.0 e-3 Xe-137

.6.17 3.86 min 451700 '1340 1.0 e-3 -j Xe-138 5.49 14.2 min 46000 1010 19.1Je-4 Br-82 0.125 35.3 h 1044. 23 0 a Br-83 0.51 2.4 h. 4270' 94 0-U Br-84 0.90' 31.8 min 7540 166J 0 1 Br-85' 1.1 2.87 'ain. 9220. 203 0 I-130m 0.51 9.2-min 4280 _ 94 0 j I-131 3.1 8.04 d 25970 571 0 I-132 4.38 2.29 h 36700 .807 0-d I-133 6.9 20.8 h 57800 1270' 0 I-134 7.8 52.6 min 65350 1440 Of l I-135 6.1 6.585 h 51100 1120 0 -I I-136-3.1 86 sec 25960 571 0' )8. The-assumption of a 120Ielement< core isttypicalsof'recent' }i operation'at the GSTR. MCNP~ analyses showLthat, with the-addition of'new'12 w% fuel, the core must have about 100 elements to. stay l A ' 'below the limit of 22 kW per element in an operational core. A-j . larger. core.would' result in-a-lower power peak. Approximately.100 j elements are required in the core to ensure the-peak power-element 1 is not producing more than 22 kW. In a 100 element core, the worst case peak to average power per element would be approximately:2.2. N In the worst case, the average fuel element temperature of an i I 6 1 ac.. ++ww<-+... -4 .-r ,.a, ,--m ,,u,. .m e a. s, e -m

vv e; w ~~w m !;

- +

,s ym 3,6 ;' , ? )., e t,- :-' v 3 rn N:y_;. % gb w', } sfn ,s, h 'N s 1 n:' 1 Ag 3 'h }.g ' ~ element) producing.22 kW:.would;be (655/1.25)1+: 25 = 549(Cf(Peaki E ,, l temp.~is1680.C from it'enf5 and axial? peaking is41;25)',"the release y 1 Y _ fraction would rise to/i3.146 x 10~4.= L(Re: GA'E-117-833)l This; I f S.gives.an effsstive increase in the fission product gasfrelease ofLa' 4, i m ~ ?, f ' factor lof.46:cverlthe. average' element that-is producing'.10 kW with itemperature-<350 C. , g.. -A numbe N f core'configurationianalyse's results.:are attached to d M this-document.- Tlie-- data ' contain the. core loading information ' (12 > n. w%; elements are? designated as such),1 heTelement power. peaking:

i t

the % error calculated for the, peaking. factors and the. . factors, maximum power produced per element. Analyses *are provided.for_'a 59' ielement 12 w% core,.the current GSTR core, and various-mixed-loading 7 cores that have been arranged to enhance; power peaking j ,s factors in the 12 wt elements. PERSONNEL EXPOSURES FROM RELEASE OF FISSION GASES t Occupational doses (arem) Public doses?(arem) j Isotope 1 hour' stay 6 hour stay 1 hour stay 6 hour mi.sy - 7

' <0 ; 1' i

Kr-83m' <0.1 <0.1. <0.1 p Kr-85m 11.0 13.9 <0.1 <0.1~ i Kr-85 0.1 _0.2 <0.1 < 0.1 - Kr-87 -102.5 118.'8,

0. 4.

0.5 Kr 455 562 126. ~2.O Li Kr-89 1385 1385 L2.2 2.3 . 0.1 <0.1 .<0.1 < 0.1 -

l Xe-131m Xe-133m' O.4

.0.5 < 0.1 - <0.1 Xe-133 15.1 20.0 <0.1 0:1= 4 Xe-135m 19.6 19.9 0.1 =0.1 Xe-135 133.2 172.5 0.3 0;4 Xe 137-1866 1866 3.0 3.1 1 C Xe 138 127.4 128.7 0.4 !0.4- ) a I TOTAL DOSE (arem). U / Occupational ~Public. ,i T Annual 6 hour CFR-i Annual H 1 hour .6 hour' CFR 1 hour stay ' stay, . Limit stay stay. . Limit l Whole Body 4115 4288 5000 8.0

8. 9' 100 1

l 4 4 ( 7 -j 'j i r

~_ -. ,;,1 ' ^l^{. a i ~ .( { M4 91 '{ N; - 4 s .s Nf .The exposure:fromJthe airborne fission product gases is, entirely. m w" .-from~exterr al (submersion) Lexposure.. LSince' the 10CFR20. submersion ' ] > - $11mits'eris based on an'infinitelradius, hemispherical cloud while a (the-reactor-room dimensions-are quite' finite,'theLoccupationalfdose; ivalues'given in the tables above are very conservative.

1 9.

The reactor room-ventilation'has both normal and emergency ~ l E . modes.'of operation. The'ncrual mode. exhausts air.at'about 900 cfm: j.- 'N 'directly.out the' stack. The emergency' mode ~is automatically initiated upon.the. detection of high airborne activityDin the! gm 3 reactor' room and it exhausts air.at:about 275 cfm throughrboth,a: prefilter and HEPA filter. Since the? reactor room air' volume'is. I approximately 12,300 ft, the emergency exhaust would move onel 3 1 room's volume of air in 45 minutes. The effective decay constant. for the emergency ventilation system is the ventilation flow rate -j 4 divided by the room volume, or-(275/12,300)' = 0.022'per minute.. 10.- The activity of Xe-135'(see-table in item.7)'was: calculated:as. follows: Xe-135 has a.6.3% yield:from thermal-fission of U-235. j The equTtion for the saturated activity of a fission-product is: 10/3.7 x 1610) A(Ci) = (3.1 x 10 . y, y, i) where 3.1 x 1010 is fissions / watt-sec, 10 3.7 x 10 is decays /sec-Ci, X-is the element power in watts, and Y is the_ fission yield. For Xe-135, A= (3.1 x 10 /3.7 x 1010)

22000-*--0.063,-

10 or A = 1160 Ci (rounded to 3-significant. figures). 11; New information from the GA safety. analysis for their'TRIGA Mk III (GA-9064) states that the iodine' isotopes remain dissolved in-the reactor water and will not be released, as.was stated.in the g initial analysis. Therefore, no thyroid doses will result from a' fuel clad-failure. We do not plan any releases of fission products i a 8 i L;.,

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I 'i 'y 7' 'to theiunrestrictedienvironment;;however,.our emergency systems j s (have been designed'to'further reduce the potential small dose that. /might be received by'a: member of the public.' The' emergency ventilation;will prevant any particulate daughter, products /from f Lbeing' discharged and an emergency alarm that' actuates.withLthe' detection:of.high airborne activity willievacuate the reactor l building'and initiate'the' emergency procedures. The emergency l evacuation-will cause offsite emergency personnel to respond, ~ causing'the~ area surrounding the rea'ctor. building to be~ secured.. 'This will prevent any personnel from being'near'th'e building, .j further reducing any possible dose to.less than the 8.9 rusam given q 'in the table of item 8. l ~ 1 7 12. The reactor emergency exhaust system is operationally. tested-1 each operating day by alarming the air monitor, before' reactor-operations are started. This is part of the daily checklist that' l is completed by the reactor. operator and health physicist.- i 13. The 6 hours stay-time was used to give a maximum possible i dose, even if personnel did not evacuate ~the reactor room.cr move away from the building. This.is not considered' credible,Jbut it l 1does provide.an extreme upper limit that still results in less than i 5000 mrem dose (occupational) and 9 mrem dose (public). A credible 1 and more realistic stay time during a fission product release would be 2 minutes in the reactor room and 10 minutes near the building. .1 l The next page is a Technical Specification replacement page. I i REFERENCES v LGA-9064 " Safety Analysis Report for the Torrey Pines'TRIGA Mark III Reactor", Gulf General Atomic Inc., January 5,-1970. 1 4 GA E-117-833 "The U-ZrH Alloy: It's Properties and Use in TRIGA x Fuel", General Atomics Inc., February 1980. 4 h 9 --,-:-a -... =. - ,.,.,..,.s., ,.,v.. - +,.-- ~-,-c,

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g,< M n. yl i _4_; o 22 .1he pool water shall be sampled for conductivity at least weekly. [ Conductivity averaged over a month shall not evnaari 5 micrmhos 2 W ~ per ' car. 'Ihis itent is.not applicable if the reactor is cxmpletely defueled and the pool ~ level' is' below the water - i treatment systest intake. D. Reactor Care ~ 1. 'Ihm care shall be'an maasehly of TRIGA stainless steel clad fuel-enriorator elements, nominally 8.5 to 12 wt,. uranium, arranged in a cla peaked array amoept for:(1) replacement of single. .l individual elements with incare irradiation facilities or uhul rods; (2) two separated experiment positions in the D through E rings, eacts occupying a mav4== of three~ fuel element positions. 'Ihe reflector'(excluding experiments and experimental facilities) shall be water or a combination of graphite and water. '1he reactor shall not be operated in any manner that would cause any.. fuel element to produce a calculated steady state power level.in excess of 22 kW. i 2. 'Ihe excess reactivity above cold critical, without xenon, shall- ] not eynaari 4.9% delta k/k with experiments in place. 3. Pbel temperatures near the care midplane in either the B.or C ring of elements shall be continuously recorded during the pulse mode l 'of operation using a standard tr=mcuaple fuel elanant. 'Ibe ; tra --x-ple element shall be of 12 wt% uranitun loading if any 12 ' j wt% Inariari elements exist in the core. '1he reactor shall not be operated in a manner which would cause the measured fuel 0 temperature to exceed 800 C.- i i 4. Power levels during pulse mode operatics) that exceed 2500 megawatts shall be cause for the reactor to the shut down pending an investigation by the reactor supervisor to determine the reason 1 a.-. = -- 2

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MCNP' ANALYSES AT THE GSTR q m 'Cota'neutronic analyses.of'the'GSTR TRIGA reactor were~ performed' 1 using the Research-Reactor Analysis Program.(RRAP)-from Atom- { Analysis,-Inc. and the Monte Carlo N-Particle Code (MCNP)-from=the i s The RRAP provides. el 'U.S. DOE Radiation Shielding Information Center.. ~ a user friendlyfinterface.for.using the MCNP code', allowing. -personnel to~quickly build aidetailed~model'of-the TRIGA reactor and' easily retrieve;and interpret the'MCNP. code output.. The.RRAP was customized.for the'GSTR after having been~ initially benchmarked j at the Oregon State. University TRIGA reactor. 'The GSTR version of the RRAP code show very' good agreement.with . experimentally determined values for neutron flux measurements, 1 -reactivity values of fuel and experiments and fuel element power density vs.~ fuel-temperature. The following-pages are data ~from a-number of core configurations that were run to show worst case f peaking in 12 w% elements or typical operating configurations.- It r appears that approximately 100 fuel elements will be: required JLn the core to ensure that no element produces more than 22 kW. The physical configuration of the core grid is show in the figure.- .t The data tables that follow have the details of numerous core configurations that were' calculated using RRAP/MCNP. ~The columns j + in the tables are described below: " GRID DESCRIPTION" describes the locations and types of materials in the individual core grid locations. All 12 w% fuel is listed'as ,i 12 w/o fuel; all other fuel is 8.5 w%. The fueled follower control m rods (FFCR) are indicated as such. The unfueled pulse rodsis not listed, but occupies core position C10. q " Serial No." refers the the serial number of the fuel rod in the I grid position. In most cases, the existing configuration of=the core was used for the 8.5 w% fuel loadings. Most of the listed 12-w% fuel elements have pseudo serial numbers since these elements do not' exist at the GSTR facility. A1 i

i. " Power factor" is the peak to average power factor calculated by j the MCNP code for the fuel element listed. " Error" is the absolute error in the calculated peak-to-average power factor calculated by the MCNP code. All calculations were performed with sufficient particles and cycles to keep all errors l below 5% (0.05). " Max power (kW)" is the maximum calculated power being produced in the specified fuel element. This number is calculated by dividing 1000 kW by the number of fuel elements in the core, multiplying this value by the power factor and then multiplying this product by the sum of the error plus 1. For example, given that Elements in core = 100, Power factor = 2.05, and Error = 0.012, then Max power = (1000/100)

2.05
1.012 = 20.746 kW I

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777 q =: y i , CORE." GRID ~ CONFIGURATION T e @*OO n.. a.

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v a-s e m !c - CASI: #1 I+ GSTR REACTOR ANALYSIS 1' 21919 5 - . (base core - 8.5 wt)L 125 elements-E Grid dewrlption Serial No. Power factor Error jMax power (kWL 13.4394 fuel rod #b1 3328 1.66 0.0124 fueLrod -#b2 9304 1.78 0.011 14.3966 fuel rod _#.b_3 3692 1.7 0 011 13,7496 r 6 fuel rod #b4 3610 1.65 0.012 13.3584 fuel rod #b5 - 3701 1.62 -0.012 13.1155 fuel rod #b6 6591 1.6 0.012 -12.9536 h fuelrod #ci 9531 1.39} 0.012 11T25T4 ~~ fuel rod ' #c11 9842 -1.45LO;012 11.7392 fuel rod #c12 -9474 1.31 0.012 11.0915 b fuel rod #c2 9843 '1.52 0.012 12.3059 fuel rod #c3 7932 1.48 0.012 11.9821 'a - FFCR IN #c4 10252 1.66 0.012 13.4394 fuel rod-~#c5 9532 1.49 0.012 12.0630 fuei'r~od #c6 120jj 1.55F.Di5 12.3059 O g fuel rod #c7 9533 1.44 0.012 11.0582 fuei rod #c8 9841 1.5 0 012 12.144_0 l' fuel rod #c9 3007 1 51 0.012 12.2250 _0.014f =8.59872 W FFCR in #di 5765_ 1.06 FFCR in #d10 5980 1.49 0.013 12.0750 fuel rod #dii 7200 1,39 0.012 -11.2534 fuel rod : #d12 79271 1.327 'O.013 10.6E7] fuel rod #d13j 5007 1.27[ 0.013p 10.2921, ~1.3l ' O.013 10.5352 fuel rod #d14 3321 fuel rod #d15 7934 122l 0.013 9.8869 fuel rod ' #d16 4096 1.24 0.013 10.0490 fuel rod #d17 5030 1.29 0.013 10.45_42_ fuel rod #d18 2374 1.27 0.013 10.2921 0.013 [ 10 5552 ~ fuel rod #d2 7928 1.3 fuel rod - #d3 7929j-1.36 0.012 11.0106 fuel rod #d4 1 3250 -1.33 . 0.012 = 10.7677 fuel rod #d5 I 3555 1.49E 0.012 12.0630 fuel rod #_d6 7931_ 1.37_ 0.012 11.09_15 fuel rod #d7 '7926 1.35 0.012 10.9296 fusi rod #d8~ 3134 1 41 0.012 -11.4154 fuel rod #d9: 7030 1.39 0.012 -11.2534 fuel rod ' #ei 4128

1.11 0.014;

-9.0043 fuel rod ^#e10 3017 1.24 - 0.013 10.0490 fueiiod #eif 38637 1.28 0.013 -10.3731 fuel rod #e12 I 3860! 1.29 ' O.013 10.4545 f fuel rod. #e13 311_6 1.22 0.013 9 8803, ~ fuel rod #e14 2445 1.19 0 013 9.6430 1.24 OIdi3Y 10.0490 i fuel rod #d53~~ 5di2 1.18bO.014 93fi5 5952 fieTrid #e16 fuel rod - #e17 3697 1.101 ' O.014 --9.6533 fEol rod #e18 6587 1.27 0.014 9.7344 I5ki 4_h19J 575i _1.13j_0.014 _ 9.1_666 fuel rod #e2 1 6843 1.03l 0.014 8.3554 fueiiod~Ne20T-~595fl 1.081 0.014 8.7610 ~ ~ I 691 0.014 fuel rod #e21 5699 7.3819 4 fuel rod. #e22 5704 0 981 0.014 7.9498 Eueirod T M3 5705 0.901 0.014 7.70f5 =

7 -. _ aN, mn o: GSTR REACTOR ANALYSIS 2 2/9/95 . (base core. - 8.5 ws). 125 elements t-1.15{ 0.014 fuel rod #e24 3361 1.1 8.9232 0.014 9.3288 fuel rod #e3 6839 fuel rod #e4 5731 1,17 0.014 9.4910 fuel rod #e5 5755 1.21 0.013 9.8058 flic!" rot ~he6 5734 1.27 OTOISI 10.2921[ ~ ~ ~ - fuel rod #e7 6840 1.29 0.013 10.4542 fuel rod #e8 3857l 1.261 0.013 10.2110 fuel rod - #e'9 56151 1.261 0.013 10.2110 ~ fue[Iod __#f1.] _ _.5720 _0yh 0.0[6[ 6.2580 fuel rod #f10 5759 0.94 l 0.015 .7.6328 fuel rod - #f11 5748 0 891 0.015 7.2268 fuct rod #f12 572% 0.80 0.015 7.2268 fuel rod #f13 57351 0.93 0.015 7.5516 fuel rod #f14 57441 0.89 0.015 7.2268 fueirdf'M15~ 5757!- 0.89 0.015 7.2268 fuel rod #f16 57176} 0.8_73 0.0154 7.0644 fuel rod #f17 5730 0.88 0.015 7 1456 fuel rod #f18 5743 0 87 0.015 7.0644 i 0.87 0.015 7.0644 fuelrod #fi9 5_7404 fuel rod #f2 5707 0.8 0.016 6.5024 fuel rod #f20 5706 0.87 0.015 7.0644 fuel rod #f21 5731 0.79 0.016 6.4211 4 0.83 _ 0.0163 6.7462 fuel rod _ #f22_[_,_ 5732j 1 fuel rod #f23 57291 0.841 0.016 6.8275 fuel rod #ff4 57851 0.81IdO16~ 6.5837 5725) 0.751 0.016 6.0966 fuelrod 525 5745 0.77j 0.016 6.2586 fuel rod #f26 fuel rod #f27 _ 5747 0 77 0.016 6.2586

f29 [i
f28 5727 0.81 0.016~1 65837 fuel rod 4

fuel rod 5741-0.82 0.016 6.6650 fuel rod #f3 5717 0.81 0.016l 6.5837 fuel rod #f30 573I6 0.82 0.016] 6.6 _650 q Me!!od _#f4_ __5_719 g 0.85_ _0.016j _ 6.9088 fuel rod #f5 5734 0.87 0 015 7.0644 fuel rod #f6 5760 0 85 0 015 6.9020 l I fuel rod #f7 5739 0.89 0.015 7.2268 fuel rod #f8 5708 n 0_03 0 015 7.5516 fuel rod #f9 57501 0.80 0.015~~ 7.2268 fueffodl#g1T~f47i~~~~0;@f 0.018 ji9 5.l542 fuel r.od_#g1_0.a 5720 0 63 5.1307 4 fuel rod #g11_ .5721 0.63J 0.018 5.1307 fuel rod.#g12_ 9473 0 67f 0 018 5.4565 I 5698)- .fuelfod_#g13_ 5736 0.62 0.018 5.0403 4 fuel rod #gi4 0 62 0.018 5.u493 fuel rod #g15 9534 0.68 0.018 5.5379 fuel rod #g16 5701 0.62 0.018l 5.0493 fuel rod #g17_j. 7878 0.69.,_0.017{ 5.6138 q j fuel rod #g18 1 5723

0. 6 31 0.018 5.1307 fi U 6[ _}#g{ {

5687i 0.62] 0.018 5682 5.0493 c fuel rod #g2 0.53 0.019 4.3206 4 fuel rod #g20 9302{ _0 65_L 0.018 5.2936 fuel rod #g21 5681! 0.611 0.018 4.9678 i

,g e GSTR REACTOR ANALYSIS, 3 2/9/95 '(base core - 8.5 ws) 125 elements I.ug. rod.,_ #g22 56764-0.58{ 0 018 0.63 5.1307 fuel rod #g23 5689 0.018 4.7235 4 fuel rod _#g24 5749 0.59 0._018 4.805_0 fuel rod #g25_. 5758 0.59 0.018 4_.8050 I fuel rod.#g26 5688} 0.57 0.019 - 4.6460 fuel rod #g27 5679l 0.54 0.019 4.4021 fuel rod #g28 5678 0.5_6 0.019 4.5651 fuel rod #g29 5684 0.52 0.019 4.2390 fuelfod #g3 5703 0.57_ 0.0194 4 64,60 fuel rod #g30 5700I 0.52 0.019 4.2390 fuel rod #g31 5688! 0.54 0.019 4.4021 fuel rod #g32 5690' O.54 0.010 4.4021 fuel rod #g33 5718 0.55 0.0191 4.4836 fuelr. d_#g34 568_5 0.55 0.0191 4.4836 o fuel rod #g3_5 5_695 0.54 -0.019I 4.4021 9 fuel rod #g30 57464 0.58 - 0.01_9 4.728_2 3 fuel rod #g4 5683 0.59 0.018 _4.8050 fuel rod #g5 5_738 06 0.018 4.8864 i f el rod _#g64 M 5715 0.6 _0pl8 4.8864 fuel rod #g7 5762 0 581 0.018 4.7235 0.62}1 fuel rod _ #g_8_[ 5722 0.018 5.04_93 06 0.018! 4 8864 fuel rod #g9 5724

n' .y .g. . CASE #2 k GSTR REACTOR ANALYSIS 1 2/8/95 12 wt, in B,c rings :100 elements GRID DESCRIPTION Serial No. Power factor Error Max power (kW) fuel rod 12 w/o #bi 7832 1.98 0.01 19.796 fuel rod 12 w/o #b2 7833 2.07 0.01 20.907 fuel rod 12 w/o #b3 7864 2.00 0.01 20.806 fu~el rod i2Wo~ilb4 7865 20'i ~0.di 2015Ci1' ~~ ~ ~ fuel rod 12 w/o #b5 7866 2.05 0.01 20.705 fuel ro(12 w/o #b6 7887 1.9 0.01 19.19 fuel rod #c1 1239 - 1.7 0.011 17.187 fuel rod #c11 1237 1.71 0.011 17.2881 fuel rod. #c12 1238 1.63 0.011 16.4793 fuel rod #c2 1240 1.71 0.011 17.2881 [ fuol rod #c3 1241 1.77 0.011 17.8947 FFCR #c4 10252 1.45 0.011 14.6505 fuel rod _12_w/o _#c5_ 7868 1.92 _ 0.01 19.392 fuel rod 12 w/o #c6 786_9 1.88 - 0.01 18.988 . fuel rod.#c7 1234 1.91 0 01 19.291 fuel rod #c8 1235 1.84 0.01 18.584 fuel rod #c9 1256 1.79 0 01 18.079 FFCR #di 5765 0.8.5 0.012 8.602 EFCN'#d10 5d50 fif~0 011 14.2551 ~ ~ fuel rod #d11 7200 1.29 0.011 13.0419 fuel rod #d12 7927 1.16 0.011 11.7276 1 fu,el rod #d13 5007 1.14 0.011 11.5254 fuel rod #d14 _ 3321 1.16 0.011 11.7276 fuel rod #d15 7933 1.06 0.012 10.7272 fuel rod #d18 4096 1.04 0.012 10.5248 fuel rod - #d17 5030 1.05 0.012 10.626 fuel rod #d18 2374 1.04 0.012 10.5248 fuel rod #d2 7928 1.07 0.012 10.8284 fuel rod #d3 >7929 1.06 'O.012 10.7272 fuel rod #d4 3250 1.09 0.012 11.0308 fuel rod #d5 3695 1.23 0.011 12.4353 f_uel rod #d6 7931 1_.15 0.011 11.6265 fuel rod #d7 7926 1.15 0.011 11.6265 fuel rod #d8 3134 1.28 0.011 12.9408 1 fuel red #d9 7030 1.2/ 0.011 12.8397 fuel rod #ei 4128 0.87 0.013 8.8131 fuel rod _.#e10_.__.. _ 3017 1.05 0.012 11.5368 10.626 fuel rod #e11 3863 1.14 0.0_12 fuel rod #e12 3800 1.17 0.012 11 840_4 fuel rod #e13_ 3116 1.18__ 0;011 11.9298 fuel rod #e1_4 2445 1.12 0.012 11.3344 fuel rod #e15 5952 1.11 0.012 11.2332 fuel rod #e16 3022 1.03 0.012 10.4236 i ' fuel rod #e17 3697 0.99 0.012 10.0188 fuel rod #e18 6587 0.99 0.012 10.0188 fuel _ rod #e1_9 57_5_1 0.93 0.013 9.4209 fuel rod #e2_ 6843 018_ 0.013 7.90_.14 fuel rod #o20 5957 0.85 0.013 8.6105 fuel rod #e21 5699 0.71 0.013 7.1923 fuel rod #e22 5704 0]4 0.013 7.4962 fuel rod #e23 5705 0.72 0.014 7.3008

h .Q b b m. F je ~~' GSTR REACTOR ANALYSIS -2 38E 12 w% in Bi-O rings. '100 elements GRID DESCRIPTION _ Serial No. Power factor Error Max powerjyd fuel rod #e24 3361 0.84 0.014 8.5176 fuel rod #e3-8839 0 83 _0013 8.4079 fuel rod #e4 5761 0.85 0.013 8.6105 a ' fuel tod #e5 5755 0.88 0.013 8.9144 ~ fuel rod #e6 5754 0.93 0.013 9.4209 fuelrod #e7 6840 0.98 0.012 9.9176 fuel rod ' #e8 3857 0.96 0.013 9.7248 fuel rod #e9 5013 1 0.012 10.12 fuel rod ;#f1 5726 0.57 0.016 5.7912 fuel rod #f10 5759 ~ 0.71 0.014 7.1994 fuel rod #f11 - 5748 0.71 0.014 7.1994 fuel rod #f12 5728 0.73 0.014 7.4022 fuel rod : #f13 5735 OJ6 _ 0.014 -7_.7_064 fuelrod #f14 5744 0.77 ' O.013 7.8001 fuel rod #f15 5737 0.77

0.013 7.8001 fuel rod #f16 5716 0.81 0.013 8.2053 fuel rod #f17 5730 0.79 0.013 8 0027 fuel rod #f18 5743 0.78 0.013

-7.9014 fuel rod #fi9 5740 0.73 ' O.014 7.4022 fuel rod #f2 5707 0.61 0.015 6.1915' fuel rod #f20 5706 0.7 0.014 7.098 fuel rod #f21 5731 0.67 0.014 6.7938 fuel rod - #f22 5732

0.64 0.015 6.496 fuel rod - #f23 5729 0.63 0.015 6.3945 fuel rod #f24 5753 0.61 0.015 6.1915 fuel rod #f25 5745 0.59 0.015 5.9885 fuel rod #f26

'5725 0.57 0.016 5.7912 - 1 fuel rod #f27 5f47 d.~55i~0I016 ISI558 ~ fuel rod #f28 5727 'O.57 0.016 5.7912 fuel rod #f29 5741 0.58 0 016 -5.6896 fuel rod #f3 5717 0.57 0.015 5.7855 fuel rod c #f30 5756 0.57 0.016 5.7912 fuel rod ' #f4 5719 0.68 0,018 5.8928 fuel rod #f5 5734 0.58 'O.015 5 887 fuel rod #f6 5760 0.6 0.015 6.09 3 fuel rod #f7 5739 0.63 0.015 6.3945 i fueliod #f8 5708 0.68. _0 015 6.902 2 fuel rod #f9 5750 0.68 0.015 6.902_ water #gi 0 0 water #g10 0 O_ water #g11 0 0, y water #g12' O O water #g13 0 0 i fuel rod #gi4 5698 0.51 0.016 5.1816 fuel rod #g15 9534 0.54 0.016 5.4864 I fuel rod #g16 5701 0.51 0.016 5.1816 fuel rod _#gi7 7_8_78 0 54_ 0 016 5.4864 2 fuel rod - #g1_8 572_3 0.53_ 0.016 5.3848 fuel rod #g19 5682 0.55 0.016 5.588 water #g2_ 0 0 fuel rod #a20 9302 0.57 0.016 5.7912 j

y3 - {th; (, w, .c m w, a p s 4 'GSTR REACTOR ANALYSIS - 3: ' 2/8/95'. Q 12 w% in B,C rings 100 elements n, . -. Sii GRID DESCRIPTION Serial No. Power factor Error Max power (kW) h; fuel rod #g21-5681 0.53 0.016 5.3848 fuel rod - #g22. 5676 0.52 - 0.016 5.2832_ fuel _ rod 1Fg23 - 5689 ~ 0.48_0017 4.8816 2 fuel rod #g24 - 5749 .0.48 0.016 4.8768 h _ #g25-0 0 water water #g26 0 0 4 water #g27: -0 0 4 water #g2_8 : 0 0 4 .y water; #g29

0 0

water : #g3 0 0 water #g30-0 0 water :#g31 -0 0 p wateri#g32 0 0 ,,3 water- #g33 0 0 water #g34-0 0 water #g35 0 0 water #g36-0 0 water #g4= 0 0 water ' #g5 0 0 water #g6 0 0 water #g7 0 0 water #g_8 0 0 water #o9 0 0 ' i r 5 r -i .I I -n I-9

g f;w"M P M % gr . iLi' ~7"~'~~"' ' ~"' ' ^ W /* 4

x c_ c

~ e r um w,

-m a kk%$s S

-4 S7 wyn : w m 1 ij ~ i 6 s s ($. a - 1, ' ~ .. CASE'#3L u s'"> d ; ~ m ,~. Lt GSTR REACTOR ANALYSIS.. Page 1 J 2/lW96 d M. [, s' <12'wW in B,C rings 100 elements: - n yr c. 91-'-l GRIO DESCRIPTION ' Serial No. Power factor Error Max power (kW) d ', ' ~ ' fuel rod 12 w/o #b1 >7832 2.01 0.011 - 20.3211 a l (, Jn ' fuel rod 12 wfo > #b2 - 7833 - 2.13 0.011 21.5343 'l fuel rod 12 w/o ' #b3 7864 2.06 - 0.011 21 0286 i m

y W

fuel rod 12 w/o 4 #b4 '7865 2.07 0.011 20.9277 N: '~ + M h[(' fuel rod 12 w/o i #b5 " 7866 2.00 0.011 20.22 fuel rod 12 w/o : #b6 -7867 1.99 ' O.011 -20.1189 'l fuelrod #ci 71239 1.77 0.012 17.9124 O fu. o_l rod _ _#c11 -1237 1.75 0 012 17 71 ] -w fuel rod #c12 ;

1238 1.73 0.012 117.5076

. *i ,l R fuel rod - #c2 ' ' 1240 - 1.81 J 0.012 18.3172 P fuelrod #c3 1241 1.84 0.012 18.6208 FFCR #c4 : '10252 1.48 - 0.012 14.9776 2 93 .0012 19.5_3_16 t fuel rod 12 w/o #c5; -7_868 1 fuel rod 12 w/o #c6 7869 1.87 0.012 18.9244 1 fuel rod #c7 1234 1.86 0.012 18.8232 fuelrod #c8 1235 1.79 0.012 18.1148 j fuel rod #ce 1236 1.83 0.012 18.5196 i l FFCR #di ' 5765 0.93 0.014 9.4302 fF6R #d10 595d 1.35 0.013 153f55 i ~ ~ fuel rod #d11t 7200 1.24 0.013 12.5612 1i ?' fuel rod : #d12 - 7927 -1.13 0.013 11.4469 9l 5007 1.11 0.013 11 2443 i fuel rod : #d13 ' o fuel rod #d14 3321 - 1.16 .0.013 11.7508' ~l fuel rod #d15-7955 1.05 0.013 10.8565 fuel rod #d16 4096 1.08 0.013 10.9404 fuel rod #d17s 5030 1.08 = 0.013 10.940i fuel rod. #d18 2374 1.12 0.013 11.3456 d fuel rod #d2 7928 1.15 d.di3 11.6495 1 fuel rod #d3 7929 1.15 0.013 11.6495 5l fuel rod #d4 3250 1.15 0.013 11.6495 j fuel rod #d5 3605 1.32 0.012 13.3584 fuel rod w #d6

7931, 1.18 0.013 11.9534_

6 fuel rod #d7 .7926 1.14 0.013 11.5482 fuel rod ' #d8 3134 1.22 0.012 12.3464 l '~ 2! fuel rod #d9- .7930 1.20 0.013 12.156 ] .fue_l rod #ei-4128 0.94 0.014 9.5316 1 fuel rod #e10 3017 0.98 0.014 9.9372 i fuel rod #e11 3883 1.04 0.014 10.5456 "Y fuel rod #e12 3860 1.05 0.014

10.647

.g ~ fuel rod #e13 3116 0.99 0.014 10.0386~ fuel tod #e14 2445 0.98 0.014 99572 fuel rod _ _ #e1_5 - 5952 1.02 0.014 10.3428_ fuel rod #e18 3022 0.95 0.014 9.633 fuel rod #e17 3697 0.96 0.015 9.744 .i e> fuel rod #e18 6587 0 94 0.015 9.541 i fu.el rod #e19-5751 0.93 0.014 9.4302 ^ fuel rod #e2 6843 0.84 0.015 8.526-- ^ fuel rod #e20 5957 0 91 0,015 9.2365 ~ .1 .a fuel rod 321 - 5699 0.11 0.015 f8155 fuel rod #e22 S704 0.75 0.015 7.8125_ fuel rod ' #e23 5705 0.75 0.015 7.6125 ~ + ~

Y,~ $ f h [ '.0 f . E ' $t l' K + 4 , ;uw : g ;,~., hllv-&d;% - Y -.' ~ + 'f" s $ 83'fy i ^ n 3 g., "#~ ~ 1 _4j i s VGSTR REACTOR ANALYSIS

Pm9e 2 2/tW95 '

{12 wC in'B,C rings .100 elemnts 1 ~ x .J, GRIO DESCRIPTION Serial No. Power factor Error - Max power (kW) j fuel rod -#e24 <3361 0.89

0.015 9.0335 l

E tod #e3 -6839 0.90 0.015 9.135 e 1 fuel rod #ed -- 5761 0.97 0,014 9.8358 fuel rod. #e5 - 5755 0.97 0.014 9.8358 O, c w,:..< .p. fuel rod - #e6 -- -5754 0.99 -0.014 10.0386 -fuelrod #e7: '6840 1.05 0.014 10.647 'N .fuelrod #e8 3857 1.02 10.014 10.3428 .q fuel rod ' #e9 - 5013 1.0_1 0.014 10.2414 g. 5726 0.60 0.018 '6.106 tuel rod - M1 fuel rod M10 5750 0.74 0.018 7.5184 'f ~ fuel rod ~ M11 5748 0.00 - 0.016 7.0104 fuel rod. M12 5728 0.71 0.016 -7.2136 fuel rod M13- '5735 0,7_0 0.016_ 7.112 fuelrod M14 5744 0.71 0.017 47.2207 ~ ' fuel rod M15 - 5737 ' O.69 0.016 7.0104 ~ fuelrod Mi6 --5716 0.06 0.017 6.7122 "~ fuel rod M17' 5730 0.71 0.016 7.2136 fuel rod - M18 5743 0.65 0.0_17 6.6105 fuel rod ' M19 - 5740 0.64 0.017 6.5088 fuel rod M2-5707 0.63 0.017 8.4071 4, 6.6105 J, U fuel rod M20 5706 0.65 0.017 fuel rod " M21 5731 0.00 0.018 - 6.108 5732 0.65 0.017 6.6105 fuel rod M22 fuel rod : #f23 -5729 0.63 0.017 6.4071 fuel rod M24 5753 0.62 0.017 6.3054 fuel rod M25 - 5745 0.64 0.017 6.5068 fuel rod M26 5725 0.58 0.018 5.9044 l fuel rod ~ M27: 5747 0.59 0.017 6.0003 fuel rod M28 5727 0.60 0.017 6.102 fuel rod ' M29 5741 0.00 0.017 6.102 i fuel rod M3 5717 ' O.63 0.017 6.4071' l fuel rod M30 5756 0.65 0.017 6.61_05 fuel rod M4 5719 0.06 0.017 6.7122 fuel rod MS 5734 0.70 0.016 -7.112 fuel rod M6 5760 0.64 0.017 6.5088 fuel rod M7 5739 0.69 0.016 7.0104 fuel, rod _#f6 5708 0,70 0,.016 7.112 D fuel rod #f9 5750 0.73 0.016 7.4168 fuel rod. _ #g1 94 2 0.45 0.02 4.59 fuel rod #g10 5720 0.48 0.019 4.8912 water #g11 0 0 water #g12 0 0 6 fuel rod #g13- ~5736 0.48 - 0.019 4.8912 water #gi4 0 0 water- #g15 0 0 j fuel rod #g16 5701 0.48 0.019 4.8912 water #g17 0 0 g water #g18 0 0 t fuel rod #g19 5682 0.47 0.02 4.794 water #g2 0 0 ) water #g20-0 0 .m 4 +

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12 w% in B,C' rings-

-100 elements. l pg .g o 11 4 c+ ; 7 GRID DESCRIPTION - Serial No. Power factor Erros Max power (kW) 3- ,JJ water #g21 0 0 2 48 0.019 4.8912 l fuel rod #g22-5676 0 j; . water #g23~ 0 0 Ji water #g24 0 'O fuel rod n #g25 5758 0.45 0.02 -4.59 9e water #g26 -' O 0 water #g27 0 0 fuelrod #g28 5678 0.41 0.021 4.1861 water ;#g29 s 0 .O water. ' #g3 0 0 'i water = #g30 0 0 fuel roa #g31 5686 -0.41 0.021 -4.1861 g water #g32 0 0 c water #g33= 0 0 water #g34 0 0 water : #g35 - 0 '0 i' water #g36 0 0 fuel rod #g4 5883 0.44 0.02 4.488 water #g5 0 0 water #g6 -- 0 0 fuel rod #g7 5683 0.45 0.02 4.59 water g#g8 O O

J water '#g9 '

O -0 ? b k h'. ' ?

q r

D rs 'f -i

4-3 I

F

- h_[I /

+ y g CASE #4 GSTR REACTOR ANALYSIC Page 1 2/8/95 412 w% in B,C rings 89 elements GRID DESCRIPTION Serial No._ Power factor Error Max power (kW)_ fuel rod 12 w/o #b1 7832 1.95 0.009 22.107 fuel rod 12_w/o_ #b_2_ 7833 2 01 0.009 22.788 fuel rod 12 w/o #b3 7864 1.98 0.009 22.448 fuel rod 12 w/o #b4 7865 1.95 0.000 '22.107 fuel rod 12 w/o #b5 7866 1.97 0.009 22.334 fuel rod 12 w/o #b6 7867 1.91 0.01 21.675 h fuel rod #c1 1239 1.73 0.01 19.633 fuelrod #c11 1237 1.7 -0.01 19.292 fuel rod #c12 1238 1.66 0.01 18.838 fuel rod #c2 1240 1.69 0.01 19.179 fuel rod #c3 1241 1.72 0.01 19.519 FFCR #c4 10252 1.4 0.011 15.003 f.uel rod 12 w/o #c5_ ___7868_ 1.76 0.01 19.973 fuel rod 12 w/o #c6 7869 1,74 0.01 19.746 fuel rod #c7 1234 1.74 0.01 19.746 fuel rod #c8 1235 1.72 0.01 19.519 fuel rod #c9 1236 1.72 0.01 19 519 FFCR #dl 5765 0.88 0.012 10.006 FFCR #d10 5980 1.24 0.011 14.086 fuel rod #d11 7200 1.16 0.011 13.177 fuel rod #d12 7927 1.07 0.011 12.155 fuel rod #d13 5007 1.05 0.011 11.928 fuel rod #d14 3321 1.15 0.011 13.064 fuel rod #d15 7933 1.04 0.011 11.814 fuel rod #d16 4006 1.06 0.011 12.041 fuel rod #d17 5_030 1.07 0.011 12.155 fuel rod #di8 2374 1.07. 0.011 12.155 fuel rod #d2 7928 1.08 0.011 12.268 fuel rod #d3 7929 1.08 0.011 12.268 fuel rod _#d4 3250 1.08 0.011 12.268 fuel rod #d5 369_5 1.21 0.011 13.745 fuel rod #d6 7931 1.11 0.011 12.609 fuel rod #d7 7926 1.07 0.011 12.155 fuel rod #d8 3134 1.15 _ 0011 13 064 fuel rod #d9 7030 1.1 0.011 12.496 fuel rod #ei 4128 0.87 0.012 9.893 fuel rod #e10 3017 0.0 0.012 10.234 fuel rod _#e11 3863 O_.92 0 O_12 10.461 fuel rod #o12 3800 0.02 0.012 10 4,01 fuel rod #e13 3110 0.91 0.012 10_._347 fuel rod #e14 2445 0.89 0 012 10.120 fuel rod #e15 5952 0.91 0.012 10.347 fuel rod #e16 3022 0.89 0.012 10.120 . fuel rod #e17 3697 0.92 0.012 10.461 fuel rod _ #e18 6587 0.0 0.012 10 234 fuel rod. #e19 _5751 0.87 0.012 9.8_9_3 fuel rod #e_2_ 6_843 0 82 _0_.0_13 9.333 fuel rod #e20 5957 0.83 0.013 9.447 fuel rod #e21 5699 0.71 _ 0._013 8.081 fuel rod _dde22 5704 0.73 0.013 SZ.400 fuel rod #e23 5705 0.72 0.013 8.195

y x, y I' ' GSTR REACTOR ANALYSIS Page 2 2/8/95 y 12 wt in B,C rings 89 elements GRID DESCRIPTION Serial Noi Power factor Error Max power (kW) fuel rod #e24 3361 0.66 0.013 9.789 i f fuel rod #e3 8839 0.86 0.012 9.779_ fuel rod #e4 5761 0.87 0.012 9.893 fuel rod #e5 5755 0.84 0.012 9.551 i weliod #e6 5754 0.9 0.012 10.234 fuel rod #e7 6840 0.94 0.012 10.689 fuel rod #e8 3857 0.91 0.012 10.347 ~ fuel rod #e9 5013 0.93 0.012 10.575 fuel rod #f1 5726 0.58 0.015 6615 [- fuel rod #f10 5759 0.63 0.014 7.178

)

L fuel red #f11 5748 0.62 0.014 7.064 i fuel rod #f12 5728 0.62 0.014 7.064 l fuel rod f!f13 5735 0.63 0.014 7.178 fueirod #f14 5744 0.63 0.014 7.178 fuel rod #f15 5737 0 62 0.014 7.06_4 fuel rod #f16 5716 0.61 0.014 6.950 fuel rod #f17 5730 0 61 0.014 6.950 fuel _r,od #f18 5_743 0,62 0.014 7._064 l fuel rod #fi9 5740 0.63 0.014 7.178 fuel rod #f2 5707 0.6 0.014 6.836 l fuel rod #r20 5706 0 62 0.014 7.064 fuel rod #f21 5731 0.58 0.015

6. 615 fuel rod #f22 5732 0.58 0.015 6.615 fuel rod #f23 5729 0.59 0.015 6.729 i

tual rod #f24 5753 0.6 0.015 6.843 fuel rod #f25 5745 0.59 0.015 6.729 fuel rod #f26 5725 0.58 0.015 6.615 Eel rod #f27 5747' O.56 0.015 6.38_7l ] fuel rod #f28 5727 0.59 0.015 6.729 fuel rod #f29 5741 0.56 0.015 6.387 fuel rod #f3 5717 0.6 0.014 6.836 fuel _ rod #f30 5750 0.59_ 0.015 6.729 ) fuel rod #f4 6719 0.61 0.014 6.950 J fuel rod #f5 5734 0 61 0.014 6 950 fuel rod #f6 5760 0.61 0.014 6.950 fuel rod #'7 5739 0.61 0.014 6.950 fuelfod_#f8 _..___5708 0;64_.0 014 _ 7.292 .j fuel rod #f9 5750 0.63 0.014 7.178 l wate. r #g1 0 0.000 l water #g10 0 0 000_ l water #g11 0 0 000 water. #g12 0, 0._000 I water #g13 Oi 0 000 f _ #g14 d O.@ water water #g15 0 0 000 wa_ter #g16 0

0. 000 t

water #g17 0 0.000 water #g18 0 0 000 water #g19 0 0.000 water #g2 0 0.000 water #g20 0 0.000

)K ;["n{ J % " ) -b ' T .e p. h r a w ldi l t ;J -t ~ L. Vl? ' - f GSTR REACTOR ANALYSIS: Page 3 2/8/95 i 4 g* -12 'wt in' B,'c rings ' ~89' elements 1 h.c t..w _1 $). GRID DESCRIPTION Serial No. Power factor Error. Max power (kW) '09: water #g211 O 0.000 water #g22 0 0.000 j [. water i #g23 - 0 0.(XX)_ J L water - #g.24 ' 0 ' O.000 ^ water #g25 0 0.000 S.- water #g26 0 0.000 water #g27 0 0.TO water #g28 'O 0.000 1 L* water #g29; 'O 0.000 'C .- i water #g3~ 0 0 000 water #g30 -0 0.000 i! F wateri#g31 - 0 0.000 water. #g32 0 ' O.000 water #g33 0 0.000 ~ water #g34 'O 0.000_ water #g35 0 0.00_0 E. water ' _#g36 0 0 000 4 water. #g4 0 0.000 water #g5 0 0.000 water. #g6 0 0.000 water #g7 0 ' O.000 - I water #g8' O 0.000 water #g9 0 0.000 /i i ) h n ) e k

g 3 ~ x CASE'#5 GSTR REACTOR ANALYSIS Page1 12 wt in B,C rings. 89 elements GRID DESCRIPT10N Serial No. Power factor Error Max power (kW) fuel rod 12 w/o #b1 7832 2.01 0.009 22.788 fuel rod e.go #b2 7833 2.05 0.000 23.241 fuel rod b#b3 7864 2.04 0.000 23.126 fuel rod 12 w/o #b4 7865 2.03 0.000 23.01_4 fuel rod 12 w/o #F5 7866 1.98 0.000 22.448 fuel rod 12 w/o #bb - 7867 1.95 0.000 22.107 fuel rod #ci 9531 1.24 0.01 14.072 fuel _od #c11 984j2 1.28 0.01 14.52,6 r fuel rod #c12 9474 1.18 0.011 13.404 fuel rod #c2 9843 1.3 ,0.01 14.753 fuel rod #c3 10038 1.40 0.01 16.j09 FFCR #c4 10252 1.46 0.011 16.585 fil rpd 12 w/o #c5 ~ _ 7868 1.88 _ 0.01 _,_. _21.335 fuel rod 12 w/o #c6 7869 1.84 0.01 20.881 fuel rod #c8 1235_ 1.86 0.01 21.108 fuel rod #c7 1234 1.81 0.01 20.541 fuel rod #c9 1236 1.79 0 01 20 314 FFCR_#d1_ 5765 0.85 _0.012 9.665 FFCR #d10 5980 1.3 0.011 14.767 fuel rod #dii 7200 1.23 0.011 13.972 fuel rod #d12 7927 1.17 0.011 13.291 fuel rod #d13 5007 1.13 0.011 12.836 fuel rod #d14 3321 1.15 _ 0 011 _ 13_004 1 fuel rod #d15 7933 1.01 0.011 11.473 fuel rod #d16 4096 1.02 0.011 11.587 fuel rod #d17 5030 1.03 0.012 11.712 fuel rod #d18 2374 1.02 _0.011 11.587 fuel rod #d2 7028 1.07 0.011 12.155 i fuel rod #d3 7929 1.08 0.011 12.268 fuel rod #d4 3250 1.1 0.011 12.496 fuel rod #d5 3695 1.23 0.011 13.972 fuel rod _ #dO_,., 7931 1.17 0.011 13.291 fuel rod #d7 7926 1.12 0.011 12.723 fuel rod #da 3134 1.21 0 011 13.745 fuel rod #d9 7030 1.19 0.011 13.518 fuelrod #e1 4128 0 81 0.013 9.219 fuel rod _#e1,0 . _ 3017 0.94 0.012 _. _ 10 689 1 fuel rod #e11 386_3 1.03 _0012 11.712 fu,el rod #e12 3800 0_.99 0.0_12 11.,257 fuel rod #e13 3116 Og_0=012 1QR16 fuel rod #e14 2445 0.96 _0012 10 916 fuel r._od_.#, e15 59_5_2 _0.97_ 0_.012 11 030 . fuel rod #e16 3022 0.84 0.012 10.689 s. fuel rod #e17 3897 0.96 0.012 10.916 fuel rod #e18 6567 0 94 0.012 10.689 fuel rod #e19 __5751 0.87 0.012 9.893 fuel rod #e2 6843 0.77 0.013 8.764 L fuel rod #e20 _ 5'557 6hi ~DTDL 95f9 l fuel rod #e21 5699 0.69 0.013 7.854 i tuel rod #e22 5704 0.69 _0013 7.854 fuel rod #e23 5705 0.67 0.013 7.626

p - p 'A. yg;y (- 3 ',' ;Q y n >n. m a r Q f, l7 5w ;y, ~g.mf,b y; l.. t c' g;2., ms n n a m 3 Qf$ hf ! l[ +\\ .[ . l ..t 's w R w w.p.t + <+ -? .k ' }'i e ' 's l i_^ : j V + +f tp. q Q~ q, z. o v ;. y +

9;wy.

s g _l 7 Pa9e 2. ' SGSTR REACTOR ANALYSIS Eh ', M, (12lw% iniB,C.; rings-.c 89' elements: f W 2% ' {1. W, M-U ,_ L.M GRID DESCRIPTION Serial No. Power factor Error Max power (kW) -j 1 yQ e.aM fW W < Wo24-' 3361 'O.79 i 0.01 3 8.992 x Q 7 fuel rod - #e3 6839 0.84 'O.013 9.561 X.i. W ,m p' tar M fuel rod 4 #e4 ' 5761 .0.84 - 0.013

9.561 F@t Elrod'We5?

' 57f5

0T5f~0 612 9.853 SN r'

4 4 fuel rod ~ #e6 :,. 5754

0.94 ; 0.012 10.680 Y. i NR.cj, +.. '+,.~

fuel rod ' #e7: 6640 0.97 s 0.012 = 11.030 a u 2 q= % '.T fuel rod r #e8 -3857 0.97 0.012 11.030 gA : fuelrod #o9 5013 0.96 J 0.012 - 10.916 l fuel rod M1.. '5726 0.54 0.015 6.158 7 s 1' fuei rod - M11 - 5748 0.86. 0.014 7.520 ]l fuel rod o M10 5759 0.89 0 014 7.861 m l fuel rod ' M12 ' -5728 0.68 ~ 0.014 - 7.747 d fuel rod - M13-5735 0.69 0.014 7.861 'I 4 v. fuo! rod M14 : 5744 0.68 0.014 7.747 .i fuel rod -> M15 5737 0.97 0.014 7.634 fuel rod M16 5716 0.86 0.014 7.520 'd k fuel rod M17 5730 0.65 0.014 7.406 I y .f 7.634 d fuel rod M18 5743 0.67 0.014 / fuel rod M19 5740 0.66 0.014 7.520 1 g fuel rod. M2 5707 0.55 0.015 6.272 i 1; ,~ fuel rod. M20 5706 0.86 0.014 7.52_0 j m k fuel rod, M21 5731 0.63 0.014 7.178 M fuel rod - M22 5732 0.63 0.014 ~ 7.178 0, fuel rod ' M23. 5735 0.61

0.014

' 6.950' i fuelIod M24, 5753 0.6 0.01 5 6.843 ^y fuel rod - M25 - 5745 0.57 0.015 6.501 4 fuel rod M26 - 5725 0.55 0.015 6.272 7i fuel rod ' M2'. 5747 0.54 0.015 6.158

j 7

1 s fuel rod-M28 "5727 . 0.55 0.015 6.272 fuel rod #f29 - -5741 0.54 0.015 6.158 w J ~' fuel rod M3 5717 <0.57.0.015 6.501 d

t fuel rod M30 5756 0.56 x 0.015 6.387

~ $015 6 615 l 0 ~ f d rod ipt4 - 5 719 ' 0.58 ~ fuel rod ' M5 ' -5734 0.50 0 015 6.729

i fuel rod > #f6 5760 0.58 0.015 6.615 fuel rod M7 5739 0.61 0.014 6.950 2 _.014 7.634 j

fuelrod #16 5708 0 67 0 2 fuel rod #f9. 5750 0.69 0.014 7.861 water #gi 0 0.000 f' water #g10 0 0.000 i D water #g11 0 0.000 i water _Wg1_.2 - 0 0300 ] water #g13 0 0.000 fj water #gid 0 0.000 l s; water #g15 0 0.000 W water #g16 0 0.000 .j water #g17 0 0.000 l vWer : #g18 'O 0.0 60' d water #g19 0 0.000 l water #g.2 0 0 000 j +1 water #g20 0 0 000 j 7, e n

.: ~ 4 -y; f e- .g.,_d, J.' ,,z p t p p.;- s s r'z' 1, p", J GSTR REACTOR ANALYSIS Page 3 12 w% in B,C; rings '89-elements-4 - ?-h GRID DESCRIPTION Serial No. Power factor Error Max power (kW) 9 water #g21' O 0.000 water #g22_ 0 0.000 ' j .;jf., water' #g23 0 0.000 water #g24 - 0 0.000 l j water #g25 0 'O.000 water #g26 0 0.000 i i water _#g27 0 0.000 water #g28 0 - 0.000 water #g29 - 0 0.000 water #g3 0 0 000 water. #g30 0 0.000 watar - #g31 0 0.000.- water _#932 - O. 0.000 water #g33-0 0.000 j.. water #g34-0 0.000 water #g35 0 0.000 water #g36 0 0.000 4 water #g4 0 0.000 Ater _ #g5 0 0.000 water #g6 0 0.000 water #g7_ _ 0 0.000 water #g8-0 0.000 water #g0 0 0.000 9 4 Y C ~f f + i or-n i t i r 1 i 1 1 4<

W p.> CASE #62 y2 b GSTR REACTdR ANALYSIS 1 2/14/95 New 8.5 wt % element in b2; 124 elements i Grid desenption Serial N,o P_ower factor._ Error. Max power {kW); fuel rod #b1-3328 1.73 - 0.011 14.1059 fuel rod,_#b2 9304 1.87 0.011 15.2474 fuel rod #b4. _ _,_369_2 1.76 _ 0.01 14.3363 fuelfod.#b3 13.6167 3510 -1 67 0.011 fuel rod #b5 3701 1.65 0 011 13.4536 fuel rod _ _ #b6 6591 1.65 0.011 13.4536 fuel rod #ci 9531 1,46 'O.011 11.9044 fuel od #c1 _ _ 9842 1 43 _p,.011 1_1p598 f fuel rod #c1 9474 1,39 0.011 11.3337 fuel rod Sc2 9843 1.54 0.011 12.5567 fuelrod #c3 7032 1.52

0.011 12.3936 FFCR in #c4 10252 1.67 0.012 13.6302 fuel rod #c5

_ 9532 1,49 _ 0.011 _12.149 fuel rod #c6 7201 1.53 0.011 12.4752 Tuel rod #c7 ,,_ _9_533 il7 0.011 11.986 fuel rod #c8 984j 1.45 0.011 11.8229 . fuel rod #c9 3007 1.49 0 011 1214_9 FFCR in #di 5765 1.06 0.013 8.66 ~ T655 11.83E6 0 ~ FFURTrisdid~ 5980 1J5 fuel rod #di 7200 1.34 0.012 10.9368 fuel rod #di 7957 1.3 0.012 10.6103 iuel rod #d1 5007 1.3 0.012 10.6103 fuel rod #d1 3321 1.31 0.012 10.6919 fuel rod #di 7933 1.22 0.012 0.9574 fuel rod #di 4096 1.23 0.012 10.039 fuel rod #d1 ' 5dio 1.3 0.01 2 10.6103 fuilIod~#di --23f4, 15~6612. idI6id3 fuel rod #d3 7929 1.35 0.012 11.0184 fuel rod #d4 3250 1.38 0.012 11.2633 fuel rod #d5 3695 1.48 0.011 12.0675 fuel rod #d0 7931 1.36 0.012 11.1 fuel rod #d/ 7926 1.34 0.012 10.9368 fuel rod #d8 3134 1 43 0 012 11.6713 fuelrod #d0 7030 1.34 0.012 10.0368 fuel rod #ei 4128 1.17 0.013 9.5587 fuel, rod _#ei _ 3_017 _ _ _1.19.. 0013_ 9.7221 2 fuel rod #ei 386_3 1.19 0.013 9.7221 fuel rod #et 3800 1.1_5_,,,_0;013 9.3953 fuel rod #ei 3116 1.16 0.013 9.477 fuel rod #ei 2445 1.14 0.013 9 3136 fuel rod #ei 5952 1.18 0.013 9.6404 i fuel rod #e1 3022 1.14 0.013 9.3136 fuel rod foi 3697 1.17 0.013 9.5587 fuel rod #ei 6587 1.21 0.013 9 8855 fuel rod #el 5751 1.12 0.013 9.1502 fuel rod #e2 5957 1.07 0 013 8.0051 fu.el od #e2

6843,

._1.09 _0.013 _t 8.7417 fuel rod #e2 5699 0.92_ 0;01 3_ 7.5163 fuel rod _#e2

5704, 0;96 _ 0.013 L _._

7.8431 fuel rod #e2 5705) 0 90r 0013l 7.8431

m-y QF A LGSTR REACTOR ANALYSIS '2-2/14/95 - New 8.5 wt % element in b2 _.124 elements-D h, - Grid description SeriaI No. Power factor Error - Max power {k_W1 fuel rod #e2 _3361 1.13 0.013 9.2319 fuel rod #e3 6839 1.19 0_013 9.7221 a fuel rod _ #e4 5761 1.19 0.012 _9.7125 fuel rod #e5 5755 1.21 0.012 9.8758 fuel rod #e6 5754 1.3 0.012 10.6103 fuel rod _ #e7 6840 1.3 0.012 10.6103 fuel rod #e8 3857 1.27 0.012 10.3655 fuel rod #e9 5013 1.23 0.012 10.039 fuel rod #f1 5720 0.81 0.015 6.6306 fuel rod #f1 5759 0 92 0 014 7.5237 fuel rod #fi 5748 0.88 0.014 '7.1066, fuel rod #fi 5728 0.88 0.014 7.1966 fuel rod _ #fi - 5735 0.84 0.015 6.8762 fuel rod #f1 5744 0.72 0.016 5.8997 fuel rod #f1 5716 0.74 0 016 6_0036 Iuel rod #f1 5737. 0.015 6.6306 2 0.81 fuel rod #fi 5730 0 84 0 014 6.8694 fuel rod, #f1 __ _ _ 5743 _.0.83_ 0.015 _6._7944 fuel rod #fi 5740 0.81 0.015 6.6300 fuel rod #f2 5707 0.87 0.014 7=1148 fuel rod #f2 5700 0.82 0.015 6.7125 b I.uelpd #f2_. 5731 Oy 0.015 6.5488' 3 fuel rod #f2 5732 0.84 0.015 6.8702 f,uel rod #f2 57_29 0.85 0.015 6.9581 fuel rod #f2 5753 0.82 _0.015 6.7125 fuelrod #f2 5745 0.81 0 015 6.6306 1 fug![od #f2 572_5 _0J6 _ 0.015 _ 6_.3851 fuel rod _#f2 5747 0.79 0.015 6.4689 fuel rod #f2 5727 0.82 0.015 6.7125 fupi od_ #f2 5741 - 0;8_1 OJ15 6;6306 l fuelrod #f3 5717 ' O.86 0.014 7.033 f.uelpd_#f3 5750 0.8_2_ 0_.015 6.7125 fuel rod #f4 5719 0.88 0.014 7.1966 fuel rod #f5-5734 0 89 0.014 7.2783 fuel rod #f6 5760 0.37_ 0.014 7.1148 a fuel rod _#f7 5739 0.93 0.014 7.6055 f.uel. rod.,_ #f8_ _. _ _5708 _ _O.05 _0J14 7.769 7 769 fuel rod #f9 5750 0 95 0.014 fuel tod_#gi 9472 0.0 0.017 4.9213 fuel rod _ #g1_.__ _ 5720 0 66 0.016 5d081 fueirod.#g 1_ 5721 _ O 62__0017 5 0853 fuel rod #gt 9473 0.67 0.016 5.49 fuel rod #gi 5736 0.01 OJ17 5.0033 fuel rod #g1 5608 0.59 0.017 4.8392 fuel rod _#g1 9534 0.62 0 017 5.0853 fuel rod _ # 1 5701 0.47 0.019 3.8626 9 Cd terrn!. us #g17 0 n fuel rod #gi 5723 0 47 0.0_19 3.862_6 fuel rod #gi 5682 0 55 _ 0_018 4.51_56 fuel rod #g2 5687 0.59 0.017 4.8392 fuel rod #g2 9302. 0 61 0 017 5.0033 i

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+ y-s g s , ug

GSTR REAC~OR ANALYSIS '

~ -3' 2/14/95' ; F"i

;tT..

ENeW 8.5 wt % element in b2 i ?l24 elements T-- E i ~ NhM, M y'[ Grid descriptiore Serial No! Power factor Error. Max power (kW) ,3l fuel rod - #g2; 5681

0.59 0.017

. 4.8392 hi. ? _ -- ;7, > fuel rod; #g2: "5676

0.59

' 0.017 4.8392 e sY l j ' ' @ L.: fuel rod - #g2 > .. 5689 0.57 0.017 4.6752 l L fuel rod #g2 : 5749

0,58

- 0.017 ~ 4.7572 i 4 Q...s.' fuel rod - #g2d 5758 0.61 ' O.017 - 5.0033

.c 4

7 fuel rod : #g2 __ -5688 - 0.58 0.017 = 4.7572 j k' fuel rod;,#g2

5679

0.55 0.017 "6

-- 4.5112 ^ fuel,r d #g2A. 567_8 -0.55 i 0.018 4.5156 ?! o a, fuel rod ' ' #g2 .5684 .' O.56 0.017 4.5932

J 0.83

" 0.017 fuel rod J #g3 5703 5.1873 ' fuel rod :- #g3' '5700 0.54 0.018 4.4335 V ' ' + . fuel rod #93 -5686 0.52 0.018 4.2693 4 p fuel rod ' #g3-5000_. ' O.53 _ 0.017..Q 4.3471 fuel rod,,,,, #l[3 5718 . 0.57

0.017 4.6752 fuelrod #g3 5685 0.50

. 0.018 -r4.5977 ' 5605 0.56 0.018 '4.59_7_7 fuel rod #g3' fuel rod #g3 : 5746 0.56 -0 017 4.5932 fuegod ' #g4 5683 0.63 0.016 5._1622 fuel rod : #g5 5738 ~ 0.63 - 0.018 5.1622 fuelrod #96 '5715 0.62 0.017 ib.0853 fuel rod #g7 '5762 0.6 0.017 4 9213 I' 5.0033 fuel, r_od #g8 - 5722 - 0.6_1 0.017 t fuel rod - #c9 - 5724 0.66 ' O 016 5.4081 s ..t

g. '?

w t. i- -1 'f _N.' su

g f CASE'#7 1; GSTR REACTOR ANAL SIS-1 2/16/05 - .' All 12 wt% core except FFCR 59 elements Error jMax power (kW) 9.R!D. D.ESCR_lPT Of{iSer al N.o Power factor fuel rod 12 w/o #bi 1111_ 1.46 0.013 25.0672 1111_4 4 fue[ rod,12 w/o __#b2_ 1111 1.51 0.0121 '25.0001 1.52_ Op12j,- _ 26.0716 fuel rod 12 w/o #b3 tuoi~roi12 UTo~#ti4}[~iiii ^ "f.48[U.~0i2[~^25.3555 l .f.uol rod,_12 w/o #b5 j 11111 1.5t O_0,12{ 25.7286 fuel rod 12 w/o #b6 l 1111 1.49 0.0121 25.5571 E fuel rod 12 w/o #c1 ~l 1111-1.28 0.014I 25~995i fue!Jod 12,w/9 511 .1111,.__ __1,.2k 0.Di[ _,_21439,1 fuel rod 12 w/o #c12-1111 1.23 0.014 21.1391 fuel rod 12 w/o #c2 1111 1 22 0 0141 20 9873 ~ 1.27DUiil FFdfin #c4 ~ 7 d555 1.04bbi5f _21.5555 fuel rod 12 w/o #c3 1111 57X9'I4 fuel rod 12 w/o~ #c5 1111' 1.32 0 0131 22.6635 fuel r'od i21v/o #c6 ~ ~ I~ i11'il - ~i.2d '~ ~ 0i4 ' ~ ~ 21 6547 fu@jki25Uc.7][__]i{i ~ ~ ~ i[3 0ldi3[^ ]22.520[1 f.uel rod 12,wlo_ #c8_ _ _1111 _,_ _1.25..._ 0.014 __21A829 fuel rod 12 w/o #c9 1111 1.23 0 014 21 1391 @RMdi. _. ]{. Sfd5f,[3d1 _0.016 [ _10.5043 4 FFCR in #d10 . L _ 5_9801 0.84, 0.0161, 14.4650 fuel rod 12 w/o #d11 1 11111 1.03 0.0151 17.7103 fuel rod 12 w/o #d12 l 1111 I 1.01 0.015 17.3753 . fuel rod 12._w/o_#d13 j 1115b,,._0.95 fuel rod 12 w/o #d14 l 1111 1.02 0.015,. . 16.355i 0.016 i 17.5473 fuei~ rod'12 w/old[i5T fi15 ~~~ di5I~~i6.i870 ~ 0 94 0 fIulir~od I2w/o #d 1111 0796 ~~d' ~i5h 15 53[4 fuel rod 12 w/o_#d17. 1111 0.99; _ 0 0151 _17.0312 fuel rod 12 w/o #d18 1111 1.04 0.0151 17.8914 ~ 5fif~~0is ~0.0[1h 1I.~0_3_if lucitod 12 w7o~ #d2 ~ ~ 1 j fuel rod 12 w/o #d33 1111 0.07 0.0151 16 6_8_71 2 fuel rod 12 w/o #d4 1 11111 0.07 0.0151 16.6871 f'uei~rodi5 w/o #d57 11 tit 1T631 fuel rod 12 w/o.#dG.[ _,1111[ _ 0.55h0.015 17.8914 fuel rod 12 w/o #d7 l 1111 1.01. 0.015 _ _17.0312 0015_ 17.3753 fuel rod 12 w/o #d8 1 1111 0 98 0 015 10 8592

ei]1 iTU{~~0di5l 17T37_53
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~ tuel rod 12 w/o fuel rod 12 w/o 1111L _0& L A 017 _ 13.7897 1 fuel rod 12 w/o #e10 1 1111 0.841 0.017 14.4702 fgel rod Mw/g_ #eij[ _ 1111 ~ .8 Oj17] i [13.7897 g__ fuel rod 12 w/o _ #e12.4_1111 1 08g.0_017 __ ;13._7897 fuel rod 12 w/o #e13 11111 0.81 0 017 13 M 21 m fiEfimili2w2Ueif,](({(ff~]8i.f @0017[ Z M 9621 fuel rod 12 w/o _#e15.4 _.1111 , _0,78. _ ; _ _ _13.445_0 f9el. rod.12 w/o ;#e16 L 1111 0.78 _ 0_017[ 13.4450 L fuel rod 12 w/o #c17 1 11111 0.761 0.0171 13.1002 tielrodI2w/o #ef5 T 1111! 68 0.d17i ~i5.Y597 Q}di2 w/o _#e1(.11Ti[._., _0 7f}} ;0.017 __ _1(2K6 ~ ~ - fuel rod 12 w/o #e2 11111 0.751 0.017 12.9278 iAIMi2 w/dWOI ^IiiU(~ ~~0 76I ~ d ,._0 017[L__13J173 i31dO'2 /.

e21,]

1111 __d]5 dbl? 13Id450 ~ fue!Jod 12 w/o f ellod 12 wlo M fuel rod 12 w/o #c23 1 11111 08 0 0171 13.7897

.g-e r. N GSTR REACTOR ANALYSIS ' 2 2/16/95. g, All 12 wt% core except FFCR 59 elements, 1 GRID DESCRIPTIO_fLiSerial NoqPower factor j_ Error _ j. Max power.{kW}. 4 ;017 0 13.9621 fuel rod 12 w/o #e24 1111 - 0.81 i s p 1-fuel rod 12 w/o ~ #e3j 1111 0.78 _0;0_17L 13.4450 fuel rod 12 w/o - #e4 :. I 1111 0.8 0.0171 13.7897 D.Uit{" ~~1155173 fuefied 52Wlo~#eS] 1 ~ 1111-07'0 O 0.017 14.4792 fuel rod _1_2 w/o #e6 1111 0 84 fuel rod 12 w/o #e7 11111 0.84 0.016 14.4650 fuel rod 12 w/o #e8 1111T'- OTf5I 0.017 13.4450 fueI~rdi1'2 w/o #e9 11T1) 0.78l - 0.017 -13.4453 ~ 'i i e 7 t i t I.- f

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CASE'#8. GSTR REACTOR ANALYSIS-~ 1 2/22/05 = 12 w/o in B2, others are 8.5. 124 elements e GRID DESCRIPTION Senal fio Power factor { Ermr.{ Max [mwer]kM fuel rod #b1 3328 1.04 0.011 '.1 3721., p 0 01 18p633 .fue[pd 12 w& #b2_ gd4L ,_2;?.2_ _0.011 13.6982 fuel rod #b3 36921 1.68 fuciiof~#ii4[ [~3'5'10 '1T72 "UOI1} if0244 1 v fuel rod #b5-i 3701 1.65} 0.011i 13.4536_ fuel rod #b6 1 6501-1.641 0.011 13.3721 1.45 0 011 12705f5 ]y{.36}[ ~ ~ fuel rod #ci l 9531I fuelrod., #c11.,_. [, _.., 984 ~ _12:2300 fuel rod #c12 9474 1.47 0.011 11.9860 fuel rod ' #c2 98431-1 52 0011 12.3938

o

[ f0]( 11.7413 1.44 0.011_ fuel rod #c3 FFCRln #c4 _ j __19252L_, 1.66,L.pM2] 13 5486 fuel. rod. #c5 - I.. 95321 ~.1.51. 0.011 l -__' 12.3121 fuel rod _#c7;__. [ _9553 il2 3 011J _ _1f.h[f5) fuel. rod._#c8 _.. _.._ 9841 1.48 0.011 12.0675 1.%.XdT2}E_.jpB6 Ef?IiTn 3 [ Z T E M 5ff5} T 1 45 0 012L _ 11.8346 FF_CR in #d10 1 5980j. fuel rod #d11 72001 1.36 0.0121 11.1000 1.29g. 0.012[t_;10.5287 ~ 1.29 0.012 10 5287 fuel rod #d12 7927 fuelLQ_pd13 _ j 5007 fuei rod #d14 l 3321 1.34i 0.012l 10.9368 fuel rod #d15 I~1933'~~ T27T~dO12I iO5655 ~ I Eki~od]lI6 ' 4dd6 1,3I^IDTdi2 TiEE955 r fuel rod #d17 6030 1.35 0.012 11.0184 fuel rod #d18 2374 1.31 0.012 10.6919 fueliod~5di f 7055[ 1.36~d.~di2}. I5.idd0 fuel rod #d3 t 79291 1.36 _0_0121_ 11.1000 fuel rod #d4 I 32501 1.34 0.0121

10.9368 fuei rod #d5 1

3595I ilf 60I' i I15515 2 ~ S k....#d0 _ _ _,_7931f _, _ _._134._pl{5 ,_,j0,9368 4 fuel rod #d7 7926 1.34 0.012 10.9366 fuel rod #d8' 3134 1 38 - 0 012 11.1000 fuof rod #.d0 703_0j I.52]O[0_12} 10.7755, fuel rod #et _4,128 L _ 1.18 0.013j _ 9.4770 9.6404 fuct rod. #c.10.......- 30171 _. 1.16. 0.0131 7 1J f3pf3 93953 I S.I b 3 52 T.MdO 5 g_ fuel rod., #.e13. ._ _ 3116.__1J7_0 013 _ 9.5587 fuel rod #e14 2445 1 14 0 013 9 3130 fikIMjj5__(] 5U55f . 1h10 013h ___~pl555 4 hia[ rod. #eis j. 3022t_ 1.16LO 013_,[ 9.4770 fuel rod #o17 i 3697l 1.181 0.0131 9.6404 fuel rod _ #e18.__[~6587{ 1.2i[~d'0]3[ 9I5555 'f ~ 1.18[ 0.012 _ _ _ 9 6309 fuel md #e19 __ L _.__5751._, L 4 fuel rod. #e2 -- !. 68431.-.

1. 08l...0 013l

. 8 8234 EE! K 5521 _._l C 5659 C _ 3 5f 3 51 ( Z Z l s if .l fue! md_.#e22_ _,,_ L_. 6704L._ 0.97 0 013 7.9247 i fuel rod #e23 1 57051 1.03l 0013 84149

= m m ~ ~% ,m Y; y ^ ;hh,cg[um;'Kw [' 7 i [ 1, g yv 3

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r2/22/051 jGSTR EACTOR ANALYSIS 4 7 '( 21 R F[A '. 12 w/o in B2; others are 8.5 : 124 elemmta

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GRID DESCRIPTION Serial No. [P,ower factor ' Error - Max power (kW). g' j ] ' 4 fuel rod " #e24 - 3361 ' 1.17 0.013 J 9.5587 y. .10,013 9.6404 7q fuel, rod _._#e3 6839 1.14. 1 fuel rod : #e4 ~ 5761 '1.17 - 0.013b 9.5587 ~ ~' fuel rod ' #c5 - ~ T ~ 5Y55 ~ 1,1570.'Dl3I ' = 0.7221 s ~ fuei rod ' #e6 5754 o1.22 20.012 9.9574 o y fuel rod _#ef 6340 1 24 -0.012 10.1206 7, fuel rod ' #e8 '3857 - 1.2 0.013 9.8038 + a-5013 _,,___.1, 8 10 Mig 9 4404 Q p, fuel,fod2.#e9 q. 1 W fuelrod #f1 5726 0.82 0.014 6.7059 9 fuel rod #t10 5759 _ 0 89 0 014 7.2783 h i 6, fuel rod. #f11, 5741. ~ 0.84 0.015 6.8782 fuel rod n #f12 ' 5728. 0.84 < 0.015 6.8762 p1 fuel rod #f13 5735! 0.8 - 0.015 6.5488 fUei'iod #f14 Stid 0.75'd.~0I6 5 89' ~7 I- ~ 9 fuel _ rod _#f15 .. 5737[ 0.74 0.016 0.0036 1 fuel rod #f16 5716 0 81 0.015

6.6306 fuel rod #f17 5730 0.82 0 015 67125 y

y fuel rod #f181 4_574g 0.86 0.014 7.0330 fuel rod #fi9 [ 57401 0.85 0.015 6.9581 s fuel rod #f2-57071 0.85 0.014 6.9512 r fuel rod #f20 L5705I-0.87 0.014

7.1148 idmd.jf21_.._._., _._. 573L 03.1 _0.015 _,,,_= 6J306 n

fuel rod - #f22 5732 0.82 '. 0.015 6.7125 ~IUI5F-

7 d359 fueirocil55~

5729 I 680-0 ~ ~~ y 6.9512 0.85 - 0 014 fuel od__#f24 g 5753 ,'r f 5745.4 [- 0.84 L0.0141 _ 6 8694 fuel md ' #f2S

_ J fue!Jod #f26 _ _

5?25 0 82 _0_0_151_.. J 6.7125 fuel rod #f27 - ' 5747 O.78f 0.015h '~ 6.3851 'O.83 _ 0.015 6.7944 fuel rod -- #f28 : 5727 i fuel rod #f29 5741 0 82i-0.015- '6.7125 fuefioifl5' -5717 0 54Q0}5]- 6.8762 ~ ~ fuel rod. #f30 _ g _,. y?56g; O 80 ( 0.015 7.0399 fuel rod #f4 - 5719l 0.86 0.014 7.0330 fuel rod #f5-5734 0.85 ' O 014 09512 f5I~ rod #f6 5750 0.84 0.014 6 8604 jue!Iod.,,,f7 _,_,1 . 5739j 0.86LO.0141 ~ 7.0330 fuel rod;#tB_ __I 57_08! _ 0.9 _0.014I 7.36_01 l ~ 01 I 5._75 4 ' 0_.91-- 0.0. _14 7.4419 f_uel rod #f9 fuel rod #g1_. _ _ 9472 0.63 _0 017j -5.1073 fuel rod 1 #g10 ' , _ 5720 0 6 _0_017 4.9213 fuel rod #gii 5721 05 0.017 . 4.7572 fuel md _ #g12 _ 9473p 0 63 J p17 _.11673 e 9 fuel rod #g13 1 57361 0. 0.017 4.8392 fuel rod #g14 I 5698 : 0.561. 0.017 4.5932 fuel rod #g15 5534~ ~iT6{65i7 4.9553 y fuel pd.#g16 _ _ j _ _5701 0.47._0 019, _ _ 13;8626 f Cd terminus (air filQ t 1 0.0000 [uMcd{#g18~ 75'f53{~~6~46{d559" i'/5D4 fueLmd_#g2._,.,[ _ 364[p, _ 0;55g _018g 4.5156 0 fuel rod _ #g19__4 5632 ._. __0,58L._0 017.C_4.7572 n fuel rod #g20 1 9302 O 61 0 0181 4.9261 1:

~ [: . rp * - 3 e -) L J g-7 L GSTR REACTOR ANALYSIS 3 2/22/05 ' 12 w/o in B2, others are 8.5. 124 ' eleinents W GR.lO DESCRIPTIOff] Serial No.. lPower factor { Error Max power (k_WL fuel rod _#g22 ~5676] fuel rod #g21 5681 0.59 0.017 -4.8392 0.62 - 0.017 5.0853 fuel.r_od_._#g23 _.. ~_ _5669 0.59 0.017 4.8392 p. fuel rod #gi5-575~8 0.57 0.017 4.6755 fuel rod #g26 1 56881 0.571 0.017' 4.6752 fuirod #g27 ~ I 56791 0.59{ _0.017' 4.8395 fuelfod #928. _ j. 5078 o 0.57 0.017 4.0752 fuel rod #g29. 5684 0.56 0.017 4.5932 fuel rod #g3 5703 0 63 0 017 5.1673 .T 5700! 0.5 6} 0.0j.7 4.5032 fuel rod #g30 p 4 9 fuel rod #g31 '_568j6 OR[ 0.0171 4.6752 i fuel rod #g32 ..... _.-56901._.. 0.561 0.017I 4.5932 fuli iod ' Itg55 j 5085f 0.'5E d557j~ 4.0752 IUII0d$A35~ __.56[95 0 58 _0 O_f7 4j512 9 Nel mL# 36__._ 5740 0 5 ._0 017 4 8392 l 9 1 3 q fue! rod,, #g4_._,_;,. 9._ O_6 0.017 p ._ 4.9213 5683 fuLei rod #g5 l 5738J 0.6f 0.0171 4.9213 57151 0 611 0.017 5.0033 fuel rod #g6~ ~5152I fuel [ hg7 O5(0.017 4.7515 fuel od.,..#g8 _ 5722 _ _. 0.6 0.017g 1 9213 4 f L fuel rod #g9 l 5724 0 611 0.017i 5 0033

g_ ,+ ,y ., l Y% / 1 k p CASE #9. GSTR REACTOR ANALYSIS .1' 2/22/05'" 12 w/o in C2. all else is 8.5 - 1125 elements-GRjD DESCRIPTION ^ Serial No. Power factoq. Error _ Max power M. fuel rod #b1 3328 1.65, 0.010 13.4378 4 4 fuel rod __ #b2 : 9304 1.78 0.018J- . 14.4963 s fuel rod #b3 : 3692 .1.73 - 0.018' -14.0891 FiS10[ ~ 1.6 ~6di8 1503U4 fuel rod ~ #b4 fuel rod #b5 37011 1.62 - 0.018 13.1933 fuel rod - #b6 = ~ 65011 1.57 0.018 12.7861 -} 955II I.5 I 59I 11.1682 fudrisd~#ci

cit _ f,9842 _,_ L44 [ A 019

'~ fuel.md _ 11.7389 fuelrod #c12 9474; 1.35_. 0.019 -11.0052 fuel rod 12 w/o #c2 1234! 1 93_- 0 019 15.7334 10252[ 1.42f _ 0.019{. i fucj rod. #c3 7032 11.5758 EFCR in #c4 __ 1 164.L 0 02L 13.3824 fuel rod #c5 I 95321 1.54i~0.018 ~~~12.5418 - - -.4. 120. 4I ~ ~~ ~155'1 0.0.f9.; 12.309. 5

co~~T 1

f.uefied ~ ~ fuel tod _ #c_7_g,_ 9533 _.__.1.42 0.019t 11.5758 4 fuei rod i #c8,_ _ 9841_,._ g46 _0 0,19..__11;9019 fuel rod #c0 3007 1 45 0 019 11 8204 5!Ni$.5._ .._,5765 _ _,J.04 0.021 8.49472 .FFCRjn #d10 59_801 _1.41 0 0211 11.5169 fuel rod #dii 72001 1.35 0.021 11.016 fuel rod #d12 7927 1.26 0.02} 10.28I6 fuel od[ M13 _ _, i _5007 _ _,__ J.26 i 0.02[.,,._,,,,_10.28J 6 f . t fuel rod

d14 _...q _. 3321 I

1.34 0.026 _.10 9344 g g ~d{6 4090h' 1.26j 0.021l 10.29T7 fud[cd !Me! md,_#d17 5030 123bO.021i 10.0466 fuel..r.od_. #d18._.-. 7 2374 1.25 0.021 10.2 fuel rod __#d3 7535 t.33L 0.02. 10.8528 fuel. rod #d4._._ 1._ 32501 1.371 0.019., _..._.. 11.1682 fuel fod h6 __.]4]@i[ _.._1 ._0 019f___11353f8 fuel rod #d7 .l 7926 1.36 0.019l 11.0867 1 fuei rod #d8 1 3134 -1 48 0 0191 12 0650

do 1.37 0 010[_

11.1682 fu}irod _ j 753[8L fue[md _#el__i 412 _ _ _t 18.lQ22] 93477 fuel rod ' #e10 I 30171 1.25. 0.0211 10.21 fueI~ rod' #e15 i_]((3863C)) { 0_02i i 103550 fuel eod_ #e_12... _ 4 _3800_ __ _1.25 _0.,02_1g___10.21 fuel rod #e13 3118. 1.17 0.0221 9.5659 Id*5I0d $ #eQ 244[5 i.] ] 15 0 022{[~5i4_024 ~ _ _1.18) 0.022j _ fuel rod _ #e15 .5052p 9.6477 1 fuel md #e13 ,_1 3022L._., _1,1_4j 0 022L_ 9 3206 .j 1 fuel rod #e17 1 3.6971 1.101 0.0221- _ _.-.0.7204 fuel md.#e_19 .. [ 57511 1.17- 0.022] 9.565_0 fuel rod #e2.. . 6843 .-.1,11 0.0221 -. 9.0754 { hhM325[ j_]ST' ~ [U '[0j22 ~ ,8 U12h 'i fuel rod #o23 1 5705 0 93 0 0221 7 6037 4

pp .) v.m E gw y.,. .L; jif f c :. m-I, GSTR REACTOR ANALYSIS. 2 2/22/95 - n 12 w/o in C2. all else is 8.5 125 elements . GRID DESCRIPTIOfi] Serial No]LPower factor { Error [ Ma i ~' fuel rod #e24 3361 1.12.y _02],. 9.1571 0 _4 fuel rod #e3 6839 1.15 0.021 9.3932

b. -

fuel rod. #c4_ ____._ 5701 _. 1.10 _.0.021 _.. _ 9.7109 . fuel rod #e6 i .57_543 1.27i 0.021L 10.3734 fuel rod #e7 1 68401 1.251 0.021I '10.21

e8

~l 385fl i~25T~6~0[2]{~ 10.5i

,e.9._ _ L.._5013[g 1 25

~ fuel rod fuel rod 0.021. _ _ _ _10.21 fuel rod ~ #ti 5726i ' O 82 . 0.025 6.724 fuei rod #f10 57591 0.94, 0 024 7.7005 fuel rod #f11 1 $N5.f 0.91}~~ ii21 fl547 fuel rod #f12 j 5728j_ 0.88L002_3j 7.2019 fuel rod #t13 5735l 0.931 0.024 7.6186 e 5M d-e m8 fuel rod _#f15_ g_; 5757h OJ bO._05k 7'.[d60 6 fuel rod #f16 5716} 0.81 -0.024 6.6355 fuel rod #f17 5730l 0 84 0 024 6 8813 E I[03. 3 b h_.555 0.82f 0.025 6.f54 D fuel rod '#fi9 l 57401 0.83J 0.025 6.806 fuel rod #f2 1 57071 0.881 0.024 7.2090 d'541 0.02h 6 55I3 fuel rod #f20 _. 5706 fuel.fod #f21. _ __t _._5731 g _ _0 7_8(0p25L,._ _ 6.396 fuel rod. #f22 1 -.732 0.83. 0.025l. 6.806 5 ~ I55{ 0.78 Tbf5f thel rp_d,,._ pfi4[ 5 6.396 fuel rod #f25 6745j. 0.82 0.025 6.724 fu.ci~roI~iti25_ -.._.._._ 57351... ._.0.76'.~..~d~d56 ^I.__ _,.5.2561 fuel rod _ #f28 E 572N 0.79j 0.025J 6.478 + fuel rod.. #f29 I 5741'.~. O.771 0 025 .6.314 EIk.Y Nk.~._ OM3MS _ __.,_,,yj00 fuel rod #t4 6719 0.87 0.024 7,1270 fuel rod #f5 I 5734 0.87 0 024 7 1270 ~i6 l Sf5Ul 055][0.024 fuctrod 6.9632 EI1kkk _._j 5739] _ 0]8j d.024 _ _._ _750iid fuel rod ~ #f8 - i 57081 0.94 'O.024 7.7005 ft ei rod #f9li_] 5750[ ~ 058[ d'02I ~ ~ f.2090 fuel rod; #g1._ .g _ 9472j 0.61 go.029, _S;0215 fuelpd._ #g10_.___ _,_5720 O M _0028 5.0989 fuel rod, #g11___ {___57219473h.___0&B _0.027 _ __._5.5869 06 _0028 4 9344 i fuel. rod _ #g12__. fue_l od__, #g13 _j 57361 0.66 - 027j 5.4226 j f 56981 0.661 J 0.0281. 5.4278 'j fuel rod #a14 9534! I 0.027I 5.6600 fuei rod #g15 fuel god _ Jg16_ . j _ _57_dif, _ _0 69 0 62 0.028 _5.0989 1 f.uel rod. #gi7 _. l.. _.78781 _._0 671 0.0271 _ _.. 5 5047 t. f.uet rod _.5g())))5685I _ _ 0.59 _0.020f 4I6555 It!ellod, #g2 __ _1 568[ _ 0 57 0.026,_ _ _ 4.68[/ j fuel rod #g20 1 9302 0 651 0 028 5 3456

4, n % p ;;p +34-

c V

3 .L t:.c [7 ' GSTR REACTOR ANALYSIS. 3: 2/22/95 12 w/o in C2. all else is 8.5 125 elements GR!D DESCR!$Ofi Serial NojPower factor Error {Maxpower(kR fuel rod #g21 5681 _ 0.0 0.020 '4 0344 _4 4 L .fue!!od,,,_#g22_ _,.j 5676 0.61LO.O_2_8 5 01_66 0 fuel rod #g23 1 5689 0.571 0.029 4.6922 fucI'r5T~itg2l4 f5740i 0.56{~0f029I 4 5560 ~ fuel rod _#g25 j 5758i 0.55l 0.029l 4.5276 fueIiof'il 27 [ ~ 5576~ 0.57{ 0.0291 4.6922 fuel rod #g26 'f 5688 ~ 0.55{DTDi9] i355d 2 fuejfod_ #g20 _,, _L,_50704 0.50; 0.03 4.0144 fuel rod #g29 l 6684 0.54 l 0.029 4.4453 fu_n,i roL#g3 1 5703 0 631.00281

51811, fuel rod #g30 5700f 0.55f 0.03]

4.532 fuel rod _# 31 1 56861

0.55j.. 0.031 4.532 9

fuel r.od #g32..-- 3. -5690l.. _.. O.561. 0.029!- -....~..6099 1 4 IU [U)9N. __.55k,~.],[d.~5,b0 059k - ,4;G9I2 fuel.{od _#g35 5695L 0,54 0.029 4.4453 57461 0 57 0 03 555f, -,__0.;56 [UlUk_.,__.4 6968 fuel rod

36 D

4_6099 fHelfod _pp4 _ __1 _ 5_38]_ 0.66 0.028L 5.4278 fuel rod _ #g5_ 7 fuot rod #g6 -1 57151 0.61 0.0281- - 5.0166 fuel rod #g7 I~5752[ dj55 idiom ['~~176@ fuel rod _, #g8,_ _ [572_2.L,_ _ 0.58[0.029. _ __4.774_6 fuel rod #g9 i 5724) 0 651 0.027 5.3404

r

.,s ..a CASE #10 GSTR REACTOR ANALYSIS 1 2/22/95 Ten 12 w/o in E4 C rings 100 elements l GRID DESCRIPTION. Serial fio IPower fachj_E~rror Max powerfw)_ l fuel rod 12 w/o #b1 7832 2.09 0.01 21.1090 fuel rod 12 w/o f*b2 7833 2.12 0.01 21.4120 l ' fuel rod 12 w/o_ #b.3_ _ _ _7864 2.15 _. 0.01 _ _ 21.7150 fuel rod 12 w/o #b4 7865 2.08 0.01 21.0080 4 21.2100 fu'el rodT2[w[o((#[~7865 2.1 0.01 f ol. rgd 12 w!.o #b6_ 7867 ._L99 _ 0.01 20 0990 H 1 12.7386 fuel rod _. #c1_._ _.9531 1.26 __0.01_g fuel rod ' #c12 ' '1238 ~ 1.63 'O.0I ~ i'8MW50 ~ ~ 1240 1 87 0 01 18 8870 fuel rod #c2~~~ fu5. rod]itc3 . _ 55 1.34_ 0011 1' 5474 7 4 FFCR in #c4 10252 1.56 0.011_ 15.7716 fUUO( N 955(.. 354 _. 0,01 ._.._13.5370~ fuel rod 12 w/o #c6 7869 1.97 0 01 19.8970 fuel od_#c7_ ._ _9533 _ _.1.33 _0.01_ __ 13J330 f fuel rod _#c8_ _. _ 1235 _ _ 1.91. _ 0 01 19.2910 fuel rod #c9 3007 1 39 0 01 14.0390 FFCR in #d1.__ _ 5_765_ _ _ _ _0.9,4 _ 0.012 ,0.5128 fuel rod #dii 7200__ 1.39 0.012 14.0668 FF.CR in #d10 _ _5980 1.20 0.011 12.7300 fuel rod #d12 7927 1.2 0.011 12.1320 fuel. fed -#d13 _._ _ 5007

1. 25 0.011

.-. 12 6375 1.18 _O.011 11.9298 fuel. rod.. #d14.. .- 3321 fuel rod #d16 4096 1.15 0.011 '11.6265 fuel rod _ #d17..._ _._ 6030 1 16 _ 0.012...__._11.7392 fu.el.. rod. #d4 _-- ___.. I _._3250 __._ 1.14 0.011 11.5254 79291 fuel rod _ #d3 i 1.17 _0.011 11.8287 fuki~ rod]_ItEG]~[ _._ 79[33 . _1Oldi . _ _ 12.132_0 fuel rod #d7 7926 1.21 0 011 12.2331 !"el!od.#d8 __ _ ___,3134 _ ___ 1 28 _0011 12 9408 3 IM9.I gd. #d9 7030 _1 22 _ 0_.011 12.3342 I fuel rod #ei 4128 0.96 0.013 9.7248 fuel rod _. #c10_ _3017. _ _1.05 _ 0 01_2_ _ 10 6260 _1 01 _0012 _10 2212 I.uel rod _.#e11_ _ _ 3863 fuel tod. #e12_._ _3800. _ _ 1 05 _ 0.012 10.3224 1_0_.6200 fuel rod #e13 3116 1.02 0.012 fuel rod #e14 2445 1 0 012 10 1200 fuel rod _. #e15 _. _5952 __ _. _1.05 __0.012 _ _ _ 10 6280 fuel rod

e16._ - [-.-

3022 -- 1.01 0.012' 10.2212 fuel od_]19 ]5f51 ___ 0 97 _0.012_ _ 9 11_64 fuel rod #e2 6843 ~ 0.84 0.013 8.5092 fudrd32{i _.[5957[ _] __,0.9_2[0[0f 14196 fuel rod _#c21 _5699 p. _ 0.79 0.013 p 8.0027 ~ 0.8l 0.013 81040 tuel rod #e22 ~6704i ~ ~0.81IO'013 ~~ ~ 52053 fuct rof#e23 5705I i

.n p ,4 L.

) [

- '. C.3 m r + t ~ GSTR REACTOR ANALYSIS 2 2/22/95 ? Ten 12 w/o in B;C rings L '100_ elements-GRID _ DEERIPTION Serial f_Jo. _ Power factor _ Error Max Ixmergw). fuel rod #e24_ 3301 0.96 - 0.013 9.7248 fugir(_.#e3 .5761 -0.94 0.013 0.5222 6839 0.93_ 0.013 9;4209 fuel rod #e4 fucilro[dl'ie5~~ '5755' O.04 ~EO1] 05222 ~ ~ e . fuel rod _#e6 5754 0.97 _0.012 9.8164 fuel rod : #e7 6840 1.05_ 0;012 10 6260 fuel rod #e8 3857 1.04 0.012 10.5248_ fuel rod #e9 5013 1.05 0.012 10.6200 fuel rod #t1 5726 0.61 -0.015 6.1915 fuel _ rod, #f10 5759 0.77 0.014 7.8078 fuel rod- #f11 5748 0.71 0.014 7.100_4 fuel rod - #f12 5728 0.74 _ 0.014 7.5036 fuelfod,,_pf13,_ _ 5735 _ _ 0_.74 _0014 7.5036 7.5036 fuel rod _ #f14 5744_ _ 0.74 0.014 fuel rod #f15 5737 0.74 0.014 7.5030 fuel rod #f16 5716 0.7 0.014 7.0980 fuel rod #f17-5730 0 74 0.014 7 5036 fuel rod #f18. 5743 0.7 0.014 7.0980 fuel rod #fi9 5740 0.7 - 0.014 7.0980 fucl rod #f2 Sfdf 0.66 0.0i'5 6.i596d ~ fuel rod #f20 5700 -0.72 0 014 7.3008 fuei roi~#fE1 5 31 0.03 d'015 6.3945 ~ fuel. rod #f 22.._.._. _.-.._5732 _ __ _._0 69. _.0.014 6.9966 fuhirod ~Ittdi-5753 0 57- ~d55 6.8dd5 0 .fUei~ rod._#t25 _..._.574S 655~if0TS. 6 5975 g g fuel rod. #f28 5727 0.66 0.015 6.6990 fuel rod ' #f29 5741 0.66 0.015 66990 fuel rod #f3_ 5717 0.64 0.015 6.4960 f_uel rod.. #f 30_.;._._ 5750___0,00 _0,0_15 _ 6.0990 1 fuel rod #f4 5719 0.65 0.015 6.5975 fuel rod #f5 5734 0 68 0 014 68952 fucijpd_#f6 5760_ 0.64 0 015 6.4060 fuel rod #f7 5739 0.68 0.014 6.8952 fuel. rod. #f.8 -.5708 -- 0.7. 0.014i- -.. 7.0550~ fuel od. pgl.._ _ __. -.. _. _ _. _ _. _ _ __0472_ _.__0. 4 8.. _.._ 0.017 4.88_16 L Wa.tgE_#g11 0.47_ _0 017 0 0000 fuel rod #g1_0__ 5720 4.7799 water #g12.,___ __ _ _ _. _. _.57360.51.. _. _..0.016 . _ _, 0.0000 j fuel rod _ #g13 5.1816 watoy,pg1_4._.. 0.0000 water #g15 00000 fuel rod #g16 5701 0.5 0.016 5 0800 0.0000 pater _.#g17 __. _. _, _ 0.0000 water #g18 fuel rod #g19 5682 0.5 0 016 5.0M)0 water _#g2_. _. _ ___ _ l _ _ 0_0000 i 1 water #g20 0 0000

~ k@hj,7Idf ' a '._._'e

ry#

r m. ,~ cp5a;ge 1 e y:qfy l =g t i j-p o y[Q::f: Q.; ' WM, ,i w k ' i :c'; - m ' - 2/22/05 .j/D; 4 GSTR REACTOR ANALYSIS i 3 !- .? 7,- iTen 12 w/o in B,C rings 100' elements'. i s t 1 wjy i;g < g( . q; GRID DESCRIPTION - Serial No;_ Power factor Error Max power (kw). l" waters #g211-,. 0.0000 ,) e o 1 fuegodi#g22 - 5676 0.51 0.017 S.1867 water e #g23 . L . 0.0000 l ... =, g;., ( water = #g24 ~ O.0000 RH" fuel rod. #g25

5758 10.48 0.017 4.8816 water : #g26_ __

- 0.0000_ ij ""j water : #g27 0.0000 g;~ fu_e_l _ rod _#g2_8_.',._. 5078_. __._0_. 44. 0.017 -4.474_8 ..g-i 1 water o #g29 i.6g{ O 0000 water : #g3.' . -j 0 0000 water - #g30 0.0000 ,l ,t fuel ro._d.#g31 - 5686 . 0.43 - 0.018 '4.3774 wate_r893.2.- _..___.0. 0. 000 water #g33-0.0000 L water # 34 -. 0.0000 9 water ' #g35 O.0000 h a water i #g36 00000 c.. f_ue._l.r,o_,d.___#.g4 - 5683 0.44 0.018 .4.4792 water #g5 0.0000 water - #g6 0.0000 -e 4 fuel rod #g7 5762 0.46 0.017 4.6782 ~ water -- L 9 - 0.0000

8

~ water #o9 -0.0000 y d 1 't t. t Y of ~ '

(w, 3 x.- w 2 2, 1th e y 7 CASE #11 GSTR REACTOR ANALYSIS ? -1 2/22/95' l Eight 12 w/o in B.C rinOs 100 elements Serial NoqPower factor _. Error Maxpo_wer [kg O GRID DESCRIPTION fuel rod 12_w/o #b1 _ 70323 2.11 0.01 ' 21.3110 fust rod. #b2 Q304 1.73 0 01 17.4730 fuyod.12,w/o _ #b3_._.__ 7064 _.. 112 _,_ 0 01_. _ _ 21.4120 fuel rod 12 w/o #b4 7865 2.15 0,01 ' 21.7150 fuel rod #b5 ~ 3f01 - 1.59' O.01 16 0590 fueT'r~od~5c~1 ~ 0.01 20.8060 7867 2.06 ~ ~ fuel rod 12 w/o - #b6~ '9531 1.27' 0.011 12 8391 fuel rod #c11 9842 1.33 0.011 13.4403 tuel rod #c12 1238 1.84 0.01 18.5840 fuel rod #c2 1240 1 92 0 01: 19 3920 fuct rod #c3 7032 1.38; O 01 13.0380 L .ilFCR in #c4 10252 1.581 0.011 15.9738 fuel rod _ #c5_ __,. _. _9532 _ _ _1. 38 _ _ 0.01 _ _,13.9380 fuel rod 12 w/o #c6 7869 1,98 0 01 19.9980 fuel rod. #c7 9533 1.34 0.01 13.5340 fuel rod #c8 1235 1.9 0.01 19.1900 fuel rod #c9 ~ 5f55 0 96 0.052 14 0390 3007 1 39 0 01 IFdifinitd1'~ 9.7153 FFCR in #d10 5980 1.39 0 011 14.0529 fuel rod #dii 7200 1.25 0.011 12.6375 fuel rod #d12 7927 1.17 0.011 11.8287 fuei.iod #d.13... 5007 1.16 .0.011 ..11.7276 fuel rod #d16 4096 1.14 0.011 11.5254 fuel rod #d1.7. - .5030 '1.14 -..0 012 . 11.5368 fuel rod #d3 7929 1.16 0.011 11.7276 fuel rod #d4 3250 1 19 0.011 12.0309 fuel rod #d5 3695 1.33 0.011 13.4463 fuel rod #dG 7931 1.21 0.011 12.2331 fuel rod #d7 7926 1.18 0 011 11.9298 fuel rod #da 3134 1 23 0.011 12 4353 fuel rod #d9 7030 1.25 0.011 12.6375 fuel rod #e1 4128 0.96 0.013 9.7248 fue! ro. d. #e10,__ _ _,3017 _ __1.02._0.012 _ _ 1_0.3_224 fuel rod #e11 3863 1.1 0.012 -11.1320 fuel od_. @12.,__ _ _.._,__ 386Q._. _,_,1,07._ 0.012 1Q8284 l fuel rod _#e13. _._ 3116 1.03 _ 0_012 10_1200_ 10 4236 fuel r_od_#e14___ 2_445 __1 _0012 fuel rod._ #e15 _ __ _59_52._ _ _1.02. _0_.012 _. _ 10.3224 fuelfod_ #e16 3022 0.97 _0.013 9.8261 fu.el rod #e17 3_697 _ 0.99 _0 0,12_. 10.0188 fuel rod #e18 6587 1.02 0.012 10.3224 I.uel rod _#e19 _ 5751 _ 0.99 0.012 _ _.10.0188 fuel rod #e2 6843 0 89 0.013 9.0157 fuel r.od._#e20 - _ _._5957.__ 0. 92 .0 013_._ 9.3196 g. f'uefied- ~ ~ ~ i~ 7 705i' ~ ~ 0811 0.013! 8.2053

e23

,w l w$w% ~ w 4My., f-u'w tW <w s W +., " ,i M M K'x~ jM 3' .1 ~ ,p@ ; n _,l..'.'..: 'l y .nsr p a ; a' J GSTR REACTOR ANALYSIS,- L2: 2/22/05, b ' %;'f 7Eight 12 w/o in B,C rings ? }100) element!s? 4 E g y ,ei ic ' GRID DESCRIPTION Serial No. Power factor Error Max power (kW) ^ - ~ '( fuel rod " #e24 3361 0.93 c 0.013

9.4209 2,,

tuel rod #e3 -6639 0.97 0.012 9.8164 4' ( ideiiod ' #e4-57557 0.96 f 076557 -9.1555 ^' tuel rod #e5 ' 5755 -1 0.012 -10.1200 { 7 0.012 10.4236 h fuel rod o#e6 _ 5'754 1.03 4 QX-fuei rod. #e7. ~ 6840 1.07 0.012 -10.8284 -.3 7~612 10.4236 Q 'idi rod 1 #e5~~~~ 3557 1.03 0 f51 rod #e9 ~' 5726 -Oli 0.015 L6.6960 hi 5013 1.03 0.012 10.4230 ~ fuei~rodT'#ff ~~ ~ e ~ fuel rod #f10 5759 0.74 0 014 '7.5036 a 't fuel rod ' #_f11 5748 0.67 _0.014 6.7038 b 5728 0.7_5_0._. 0_14 7.6050_ f._uel rod. : #f12.. ,:iI f9?lLod

f13_._ _ _ 5735 __ 0.73 10.014

. 27.5030 7.4022 fuei rod #f1_4 5744 0.74 0.014 .f_uel rod #f15 57.37 0 75.. 0 014 7.0050 fuel rod 4 #f16 5716 0.7 0.014

7.0980 J:N

i fuel rod _ #f177 573_0

_ 0:73 0.014 -7.40_22 j f.uel rod _. #fis.__ 5743 0.7. 0.014 ' 7.0980 fuel rod. #f2 5707 ' O.7 0.014 7.0980 fuel rodI#f20 5706 0.72 0.014 7.3008 fuel rod ' #f21 ~ -5731 0.63 0.015 - 6.3945 ~- fuel rod #f25 ~ ~ 5732 0 69 0.014 6.iSii6' ~ N' fuel rod. #f23' 5755 ~ ~~i)T5 6I9020 OI58 0. fuel rod - #f24 5_7,53 ' O.68 : 0.015 6.9020 fuel rod wf'251 5745 0.68 _0.014 6 8952 9 I5fiodlif5ii[ _ 5755 i 0;62_Op15 8.563'd l 4 fuel rod i #f27-5747 0 65 0.015 6.5075 ~ fuel rod #f28 ' 57277 ' O.66 0.015 6.6990 fuei rod #f29 57Ai I O.65~E615 6TS97fi ~ fuel rod #f3 5117 0.67 0.015 6.8005 fue.l..r.od__#f.3_0_._.._ -. _$.5_0_._..__6_ii_$. ~.T_ _01._5 0.5975 l fuel rod - #f4 5719 0.09 0.015 > 7.0035 fuel rod #f5 5734 0 71 0 014 7.1994 fuel rod #f6 57_60 0 68 0.014 8.8052 A fuel rod #f7 5739 0.73 0.014 c 7.4022 f.uel. rod #f8 -.-. _.~5708 0.74 - 0014 7,5036 fupifod. #g1,y _ _ 94?2 Od9 _.0_.01.7 4.9_833 fuelrod 310 5720 0.5 0.016 5.0800 2 water #g11 -O_0000 watet #g12 _, _.. 0.0000 + fuel rod (#g13 ~ 5736 0.51 L 0.016 '5.1816 water #gi4 0.0000 5 water #g15 -0.0000 4 E fuel rod #g16 5701 0.51-0.016 5.1816 .watet. #g17 0_._0000 ~ ' water : #g18 0.0000 fuel rod #g19 5682 0.51 0.016 5.1016 watet #g2 0.0000 water #a20 0.0000 w

.pg n., -- ,a' .y

,i '

4:.

.a r i .j r

GSTR REACTOR ANALYSIS ~

3 - 2/22/05-' Eight 12 w/o in B,C rings 100 elements 1 GRID DESCRIPTION _. Serial No. Power factor Error Max power _(k_W). ') watpr #g21 0 0000 t I.uelyod i#g22 5676 0.6 0.,017 S.06SO I watet #g23 0.0000 water #g24 0.0000 . fuel rod #g25 5758 0.49 0.017 -4.9833 water #g26 0.0000 water #g27 0.0000 p t' fuel [od., #g28 5078 0.45 0.017 4.5705 water #g29 0 0000 ( water #g3 0 0000 water #g30 0.0000 fuel rod _#g31 5686 0.44 0.017 4.4748 water _#g32 _ _ _,0.0000 water #g33 00000 water #g34 0.0000 J water #g35 0.0000 watg!__#g36- . 00000 fuel.[od,_#g4 _,____ 5683_ 0.47 _ 0.017 _ 4 7799 water #g.5 0.0000 . ater #g6 1 0.0000 w fuel rod #g7-5762 0.48 0.017' _ 4 8816 watet g8 0.0000 water #g9 0.0000 i - - - _ _ _ _ _ _ - - - - - - _ _ _ _ _ _ - _ _.}}

ML20080Q629

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