View source for AEP-NRC-2017-02, EP-CALC-CNP-1602, Rev. 0, Containment Radiation EAL Threshold Values.

{{Adams
| number = ML17146A078
| issue date = 10/07/2016
| title = EP-CALC-CNP-1602, Rev. 0, Containment Radiation EAL Threshold Values.
| author name = McCain S
| author affiliation = American Electric Power
| addressee name = 
| addressee affiliation = NRC/NRR
| docket = 05000315, 05000316
| license number = 
| contact person = 
| case reference number = AEP-NRC-2017-02
| document report number = EP-CALC-CNP-1602, Rev. 0
| document type = Environmental Monitoring Report
| page count = 18
}}

=Text=
{{#Wiki_filter:**Cook Nuclear
* Pla.!nt (C:NP) .*contain.m*ent Radiation EA'L .T:hre.sih:*old Val 1 uce-s p .. 1602 Revision 0 Document Author: Scott McCain Consultant, CMCG Technical Reviewer:
Kevin'Simpson
* DocuineritAuthor:
Technical Reviewer:
ERM Approval:
EP SUpervisor, D.C. Cook EPM Approval:
Ron *Sieber EP Manager, O.c. Cook 
'fitt fflFt"b"'I.
CNP EAL Technical Bases Calculations 
-CHRRM FPB Series Table of Contents 1. Purpose/Objective 
.............................................................................. 
.' ..................................
2 2. Development Methodology and Bases ..................................................................................
3 2.1. Fuel Clad Loss .............................................................................................................
3 2.2. Reactor Coolant System Loss ..................................................................................... 
.4 2.3. Containment Potential Loss ..........................................................................................
4 2.4. Decay Considerations 
..................................................................................................
5 3. Design Inputs ........................................................................................................................
6 4. Calculations 
..........................................................................................................................
8 4.1. Fuel Clad Damage Estimate Based on 300 &#xb5;Ci/cc DEl-131 .........................................
8 4.2. CHRRM Readings for the FPB Thresholds 
...................................................................
9 5. Conclusions 
........................................................................................................................
1 O 6. Rererences 
.........................................................................................................................
11 Attachments Attachment 1, 300 &#xb5;Ci/gm DEl-131 Equivalent Clad Damage ...................................................
12 Attachment 2, FPB CHRRM Readings ......................................................................................
13 Attachment 3, EVAL-RD-99-11 Bases lnformation 
....................................................................
14 EP-CALC-CNP-1602 Page 2of18 Revision 0 CNP EAL Technical Bases Calculations 
-CHRRM FPB Series 1. PURPOSE/OBJECTIVE The Cook Nuclear Plant (CNP) Emergency Action Level (EAL) Technical Bases Manual contains background information, event declaration thresholds, bases and references for the EAL and Fission Product Barrier (FPB) values used to implement the Nuclear Energy Institute (NEI) 99-01 Rev. 6 EAL guidance methodology.
This calculation document provides additional technical detail specific to the derivation of the FPB containment high range radiation monitor (CHRRM) readings developed in accordance with the guidance in NEI 99-01 Rev. 6. Documentation of the assumptions, calculations and results are provided for the values associated the NEI 99-01 Rev 6 Table 9-F-3, PWR EAL Fission Product Barrier Table, thresholds listed below.
* NEI Fuel Clad Loss 3.A
* NEI Reactor Coolant Loss 3.A
* NEI Containment Potential Loss 3.A 2. DEVELOPMENT METHODOLOGY AND BASES 2 .1 . Fuel Clad Loss Guidance Criteria Per NEI 99-01 Rev 6, this radiation monitor reading corresponds to an instantaneous release of all reactor coolant mass. into the primary containment, assuming that reactor coolant activity equals 300 &#xb5;Ci/gm dose equivalent 1-131. Reactor coolant activity above this level is greater than that expected for iodine spikes and corresponds to an approximate range of 2% to 5% fuel clad damage. Since this condition indicates that a significant amount of fuel clad damage has occurred, it represents a loss of the Fuel Clad Barrier. The radiation monitor reading in this threshold is higher than that specified for RCS Barrier Loss threshold since it indicates a loss of both the Fuel Clad Barrier and the RCS Barrier. The reading should be determined assuming the instantaneous release and dispersal of the reactor coolant noble gas and iodine inventory, with RCS radioactivity concentration equal to 300 &#xb5;Ci/gm dose equivalent 1-131, into the primary containment atmosphere.
CNP Bases The Fuel Clad FPS threshold value is based on an instantaneous release of all reactor coolant into the containment at an activity equivalent to 300 &#xb5;Ci/cc DEl-131. NUREG-1940 Table 1-1 equilibrium core activity was used to develop the site specific source term that correlates 300 &#xb5;Ci/cc DEl-131 to a% fuel clad damage value. That% fuel clad damage value is ratioed to a CHRRM reading for 100% clad damage to establish the Fuel Clad FBP threshold value in R/hr. EP-CALC-CNP-1602 Page 3of18 Revision 0 CNP EAL Technical Bases Calculations 
-CHRRM FPB Series 2.2. Reactor Coolant System Loss Guidance Criteria Per NEI 99-01 Rev 6, this radiation monitor reading corresponds to an instantaneous release of all reactor coolant mass into the primary containment, assuming that reactor coolant activity equals Technical Specification allowable limits. This value is lower than that specified for Fuel Clad Barrier Loss threshold since it indicates a loss of the RCS Barrier only. The reading should be determined assuming the instantaneous release and dispersal of the reactor coolant noble gas and iodine inventory, with RCS activity at Technical Specification allowable limits, into the primary containment atmosphere.
RCS activity at this level will typically result in primary containment radiation levels that can be more readily detected by primary containment radiation monitors, and more readily differentiated from those caused by piping or component "shine" sources. If desired, a plant may use a lesser value of RCS activity for determining this value. In some cases, the site-specific location and sensitivity of the containment radiation monitor(s) may be such that radiation from a cloud of released RCS gases cannot be distinguished from radiation emanating from piping and components containing elevated reactor coolant activity.
If so, determine if an alternate indication is available.
CNP Bases The RCS iodine activity for a pre-existing iodine spike is based on the Technical Specification 3.4.16 limit of 60 &#xb5;Ci/gm of dose equivalent 1-131 during normal operations.
The% clad damage equivalent to 60 &#xb5;Ci/gm DEl-131 is determined by ratio to the% clad damage equivalent to 300 &#xb5;Ci/gm DEl-131. That% fuel clad damage value is ratioed to a CHRRM reading for 100% clad damage to establish the Fuel Clad FBP threshold value in R/hr. 2.3. Containment Potential Loss Guidance Criteria Per NEI 99-01 Rev 6, this radiation .monitor reading corresponds to an instantaneous release of all reactor coolant mass into the primary containment, assuming that 20% of the fuel cladding has failed. This level of fuel clad failure is well above that used to determine the analogous Fuel Clad Barrier Loss and RCS Barrier Loss thresholds.
NUREG-1228 indicates the fuel clad failure must be greaterthan approximately 20% for there to be a major release of radioactivity requiring offsite protective actions. For this condition to exist, there must already have been a loss of the RCS Barrier and the Fuel Clad Barrier. It is therefore prudent to treat this condition as a potential loss of containment which would then escalate the emergency classification level to a General Emergency.
NUREG-1228 provides the basis for using the 20% fuel cladding failure value. Unless there is a site-specific analysis justifying a different value, the reading should be determined assuming the instantaneous release and dispersal of the reactor coolant noble gas and iodine inventory associated with 20% fuel clad failure into the primary containment atmosphere.
* EP-CALC-CNP-1602 Page 4 of 18 Revision 0 CNP EAL Technical Bases Calculations 
-CHRRM FPB Series CNP Bases The Containment FPB threshold value is based on an instantaneous release of all reactor coolant into the containment at an equivalent of 20% clad damage. That % fuel clad damage value is ratioed to the CHRRM reading for 100% clad damage to establish the Containment FBP threshold value in R/hr. 2.4. Decay Considerations Guidance Criteria Fission product barrier thresholds and their associated EALs are only applicable when the plant is in Hot Shutdown, Startup, or Power Operation mode (known as the hot operating modes). Per NEI 99-01, the events for these thresholds correspond to an instantaneous release of all reactor coolant mass into the primary containment.
CNP Bases There is no decay correction applied to the source term used to determine the % damage. This is based on the assumption that the LOCA and dispersion of activity within containment occur instantaneously from a critical reactor. EP-CALC-CNP-1602 Page 5 of 18 Revision O CNP EAL Technical Bases Calculations:--
CHRRM FPB Series 3. DESIGN INPUTS 1. General Constants and Conversion Factors 3.1.1. 453.597 cc per lbin water conversion factor 3.1.2. Rated Power
* Standard Plant (NUREG-1940 Section 1.2.4) .............................................
3,000 MWt
* Unit 1 (UFSAR 3.1.1) ......................... , .... ,., ................................................. 
,3304 MWt
* Unit 2 (UFSAR *3.3.1.3.1) 
..............................................................................
3468: MWt 3.1.3. RCS Liquid Volume (UFSAR Table 4.1-1) . . . ***.* 3
* Unif1 .............................................................................................................
1*1,990.ft 
*.* Onit 2 ........................................................ 
;* ....................................................
12,0.1'9 ft 3 3.1.4, NOT Data Sheet6)
* Unit *1 ............................. " ............... 
; ................................................................................................... 
;571&deg;
* Unit 2 ..........................................................................................................................
514&deg; 3 .. 1.5. Density Correction C1-tHP-6020"CHM-122Figure1)
* 571&deg; (interpolated from 568&deg; ahd 5726&deg; table values) .................. , ....... 44.5338 lbm/ft 3
* 574&deg; (average of572&deg; arid 576&deg; table values) ................................... 
; ........
Jbm/ft 3 3.2. Source Term 3.2, 1. Core Release Fraction -CRF (NUREG-1228 Table4.1l ORF represents the fraction of radioactive material released.from the fuel pin cladding and/orfLlel pellet by fission product type or chemical grouping, The CRF fdr i::duel clad failure (gap release) scenario for Halogens (I, Br) is 0.02 (2%). 3,2.2. Iodine EqUilibrium 
*Core Activity (NUREG-194d Table 14) . 
.. ::;i ;1:::131 2.67E+04 
,, 1..:133::
5A2E:+04 '1 n;134 5 .. 98E+04 5.18E+04 Page*6of18 RevlSion o CNP EAL Bases Calculations 
-CHRRM FPB Series 3.3. Iodine Conversion Factors ,-ICF(Tf D.,14844 Table Ill)
* 5.35E+04 1,,1:.135 L24E:+05 I Page? of1B Revision 0 r I CNP EAL Technical Bases Calculations 
-CHRRM FPB Series 4. CALCULATIONS 4.1. Fuel Clad Damage Estimate Based on 300 &#xb5;Ci/ccDEt-131 4.1.1. 100% Core Activity EqoivaleritReactorCoolanUodine Concentrations . . (&#xb5; .1 ) _ActivitYcore-i(Ci/MWt)
X Unit(MWt).x 10 6 AetivitJrRCS100%core-i Ci cc -v* l ( ) 0 RCS CC 3:6,7E+05.
3.83E+05 5.33E+05 5.57E+05 7.45E+05 7.78E+05 822E+05 8.58E+.05 7;12E+05 7.44E+:05 4.1.2. 1 on% Fuel Clad Activity Equivalent Reactor Coolant Iodine Concentrations ActivitYncs 1 oo%Clad-i(&#xb5;Ci/cc) 
= ActivitYncs 1 oo%core-i(&#xb5;Ci/
cc) X CRF . . *
* i.;1.:.135 1.42E+04 1.49E+d4.
4.1.3. 100% Fuel Clad Activity Equivalent Reactor Coolant DEH 31 *Concentrations ActivityRcs 1 oo%DEI(&#xb5;Ci/ci:) 
=I ActivitYRcs 1 oo%cladi(&#xb5;Ci/cc) x DE! lCFi The DEl-131 value for each iodine isotope isdetermined as follows: . . TID 14844 Table III Iodin,e Conversion Factori(Rad/Ci)
DE/ ICFi = TID 14844 Table m Conversion Factdr1-13t(Rad/Ci) 
** 1-131 7;34E+03 7.67E+03. 
<
3.86,E+02 4;03E:!:02 
'\:t;;.133 4.03E+03 4.21E+03 . ;;1;134 2.78E+02 I 2;90E+02 d'. >1:::135 1.19E+03.
1.25E+03 . T6.tal 1.32E+04 1.38E+04 EP:.cALC.:CNP.::1602 Page 8of1a* Revision a CNP EAL Technical Base$ Calculation.s -Cl-IRRM FPl3 Series 4.1.4. % Fuel Clad Activity Equivalent Reactor Coolant at 300 &#xb5;Ci/g DEl-131 300&#xb5;Ci/cc 
%Clad Damage = *.* . . . . . . . RCS ActnntYioo%DEl(&#xb5;Ci/cc)
See Attachment 1 for the spreadsheet calculations that develop the fuel clad source term activity and the % clad damage. 4.2. CHRRM Readings for the FPB Thresholds EVAL-RD-'99..:11 is utilized as the basis for associating tHe contaimneht high range radiation monitors to a particular amount of clad damage. See Attachment 2 for the derived CHRRM threshold values. See Attachment 3 for the applicable portions of EVAL-RD-'99-11 that support the E:AL threshold value dedvations.
4.2.1. Containment Potential Loss {.20% Fuel Clad Aetivity CHRRM Reading) CHRRM20%(R/hr) 
= CHRRM100% (R/hr) x 0.2 I
* VP.A 6,261::+/-03 6.26E+03 l'.:VRA1310/231ff'(612'l R11E+03 9.11E+03 4.2.2. FLielCla:d*Loss (300 UCi/cc DE1"131 ActivitY CHRRM Reading) CHRRM300 &#xb5;ci/ccDEI-1:31.CR/hr) 
= CHRRM100% (R/ht) x % Darnage3oo&#xb5;ci/ttDE1-131 Ur:litt . * .>Unit 2 .. V'RA14tOl2:410' 650'. 7.10E+02 6,80E+02 . VRA.13.10/2310 612' : 1.03E+03 9.90E+02 4.2.3, Re*actorCdolanHRCSTS Activity CHRRM Reading) .* . . . .. . . .* .. . 60&#xb5;Ci/cc %Clad Damg.ge = CHRRMsoo &#xb5;cifcc nl!:i-131 (R/hr) X 300 /l.Ci/cc 650' .1,361::+02 VRA1310/2310:
612' 1;98E+02 EP.:.CALC:-CNP;.1602 Page 9of18 Revision 0 CNP EAL Technical Bases' Calculations""" CHRRM<FPB Series 5. CONCLUSIONS 5.1. 300 &#xb5;Ci/gm DEl-431 is equivalent to:
* Uriit 1 ............................................................................
2.27% fuel Clad (gap) damage
* Unit 2 ............................................................................
2.17% fuel. clad (gap) damage 5.2. EAL Fission Product Barrier thresholdvalues are as follows: .. Rue1c1ad . , ; . 
** < . 
.:<:: , VRA14t()\(650') 
.. 7.1 OE+02. ; (R/hr): '.:'.'iVRA13tQ 1.03E+03 -Qni(?!'
6.BOE+o2 ''(R/hr)/_ 
* '*:VRA2310 9.90E+02 RCS, : *.*. . . <<
Lost. 1.42E+02 6,26E+03 2.07E+02 9.11E+03 1.36E+02 6.26E+03 1.98E+02 9.11E+03 -*-. ----Based on monitor accuracy/readability, hurnan factors and.the similarity Of results for each unit; the EAL Fission Product Barrier thresholds are established as follows: VRA1410/2410:"."" Rlhr; 650' : 700 HO .. 6300 VRA1310/2310,.:.Rfhr 6:12'. 1000 200 9100 EP'-CALC-CNP-'1662 Page 10of18 Revisiono CNP EAL Technical Bases Calculations 
-CHRRM FPB Series 6. RERERENCES 6.1. NEI 99-01 R6, Methodology for Development of Emergency Action Levels, November 2012 6.2. NUREG-1940, RASCAL 4, Description of Models and Methods, December 2012 6.3. NUREG-1228, Source Term Estimation During Incident Response to Severe Nuclear Power Plant Accidents, October 1988 6.4. NUREG-1465, Accident Source Terms for Light-Water Nuclear Power Plants, February 1995 6.5. TID-14844, Calculation of Distance Factors for Power and Test Reactor Sites, 03/23/62 6.6. Cook Updated Final Safety Analysis Report, Revision 26
* Unit 1 UFSAR Section 3.1.1
* Unit 2 UFSAR Section 3.3.1.3.1
* UFSARTable4.1-1
: 6. 7. 12-THP-6020-CHM-101, Reactor Coolant System, Revision 41 6.8. 1-THP-6020-CHM-122, Unit 1 Reactor Coolant System Chemical Addition, Revision 5 6.9. EVAL-RD-99-11, Evaluation of Radiation Monitoring System Setpoints, Rev 0 6.10. Radiological Consequences of Accidents for the Donald. C. Cook Nuclear Plant Units 1 and 2 Using Source Term Methodology from NUREG-1465, Engineering Report, Westinghouse Electric Company, October 14, 1999 EP-CALC-CNP-1602 Page 11of18 Revision 0 Attachment 1 .... I .... Q) :c 111 () .... q:: '(j 'oot *-Q) *-en > Q. > Cl) C> < 3: .sl< UJ Q) :!: <n e ...... 0::: .... -:::> 0 *-.... 0 *-z () :::> (.) 1-131 2.67E+04 8.82E+07 1-132 3.88E+04 1.28E+08 1-133 5.42E+04 1.79E+08 1-134 5.98E+04 1.98E+08 1-135 5.18E+04 1.71E+08 Total 2.31E+05 7.64E+08 Volume Conversion (cc/lbm):
Halogen Release Fraction:
Target DEi: ";-.... .!!! .c !II 0 .... q:: *c; "<t *-Q) *-(1) > Q. > Cl) +:I Q) () -< f! (i) ell .........
::::> 0 *-N 0 *-z (.) ::> () 1-131 2.67E+04 9.26E+07 1-132 3.88E+04 1.35E+08 1-133 5.42E+04 1.88E+08 1-134 5.98E+04 2.07E+08 1-135 5.18E+04 1.80E+08 Total 2.31E+05 8.02E+08 Volume Conversion (cc/lbm):
Halogen Release Fraction:
Target DEi: EP-CALC-CNP-1602 300 &#xb5;Ci/gm DEl-131 Equivalent Clad Damage Unit 1 e *-(.) .:: 00 <1;0 .... en o (,.) 0 0:::::.: .... (,.) ::> .:; a: = c -0 Q) *-*-C> -> 0 .c Q) !II > .... c <1;0 0 .... Cl) u 00() 111-u. 'oot Cl ... *-(.) (.) (J .... c 0 (.) 0::::::: . *-0 :0 .... (.) 9"n1111 w ::> .:; I-!:! LI.. ..:.. Cl 3.67E+05 7.34E+03 1.48E+06 1.00E+OO 5.33E+05 1.07E+04 5.35E+04 3.61 E-02 7.45E+05 1.49E+04 4.0 0E+OS 2.70E-01 8.22E+05 1.64E+04 2.50E+04 1.69E-02 7.1 2E+05 1.42E+04 1.24E+05 8.38E-02 3.18E+06 6.36E+04 453.597 Rated Power (MWt): 2.0% RCS Liquid Vol@ NOT (ft3): 3.00E+02 Density@ NOT (lbm/ft3):
RCS Liquid Vol @ NOT (Ihm): RCS Liquid Vol @ NOT (cc): % Clad Damage: Unit2 e a: = c -0 
.!!! *-(.) *-C> .c Q) !II > () 0 () 0 .... c < 0 <1;0 0 .... .... Cl) 0 Cl) 0 00(.) I!?-LI.. (.) () (.) 0 '<t' Q) *-0::: 5* 0::: :::: T" c 0 N (.) I *-t> "Q jjj N ::1. e" Ill 111 :::> .::: .... !:! u. ..:.. Cl 3.83E+05 7.67E+03 1.48E+06 1.00E+OO 5.57E+05 1.11E+04 5.35E+04 3.61 E-02 7.78E+05 1.56E+04 4.00E+OS 2.70E-01 8.58E+05 1.72E+04 2.50E+04 1.69E-02 7.44E+05 1.49E+04 1.24E+05 8.38E-02 3.32E+06 6.64E+04 453.597 Rated Power (MWt): 2.0% RCS Liquid Vol @ NOT (ft3): 3.00E+02 Density@ NOT (lhm/ft3):
RCS Liquid Vol @ NOT (Ihm): RCS Liquid Vol @ NOT (cc): % Clad Damage: Page 12of18 7.34E+03 3.8 6E+02 4.03E+03 2.78E+02 1.19E+03 1.32E+04 3304 1.19E+04 44.5338 5.30E+05 2.40E+08 ...... w c Q. 
*-C> uo <0 .... Cl) () (.) u 0::::::: N (.) :::> .::: 7.67E+03 4.03E+02 4.21E+03 2.90E+02 1.25E+03 1.38E+04 3468 1.20E+04 44.3169 5.33E+OS 2.42E+08 f. ?'-% Revision 0 Attachment 2 EP-CALC-CNP-1602 Unit 1 100% Clad Damage (Rlhr) VRA1410/2410 (650'): 3.13E+04 VRA1310/2310 (612'): 4.56E+04 Containment Potential Loss Threshold VRA 1410/2410 (650'): VRA1310/2310 (612'): Fuel C l ad Loss Threshold VRA1410/2410 (650'): VRA1310/2310 (612'): RCS Loss Thresho l d VRA1410/2410 (650'): VRA1310/2310 (612'): Conta i nment Potent i al Loss: Fu e l Clad Loss (300 &#xb5;C i/cc): R C S Loss (60 &#xb5;C i/cc): 20% 2.3% 0.5% Page 1 3of18 Unit2 (Rlhr) 3.13E+04 4.56E+04 20% 2.2% 0.4%. FPB CHRRM Readings Revision 0 Attachment 3 EVAL-RD-99-11 Bases Information RM11tn1 .!.. ___ __.f! ......... n ......... 1 _____ .2 C Up,-Con l.UW'i lll"l l High Rlill pci NIM. Th *It a RO Sl1 fllC)ilOf 
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lsai.-n: EP-CALC-CNP-1602 Page 14of18 Revis i on 0  
----------------------
----------Attachment 3 EVAL-RD-99-11 Bases Information A2.4. RNUb Rofdoli: 0 AUACHMIHTA Kf-86M 1<'ilS Kr I The don "* r. AANi
* 642E4 ITlltfl\tlf.
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* ealUll*I lllt la rncd9lod u o ey11ndc-r w'dl a r..tlu1<I616 
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with 1n inner nd&a of<< 5 ft. and an ou'1t' raillut c' 57.S leoet Md a efteti\-e hc1gli of 15' .2 lltt. 3. It la 8-.mod f\Ot neh ranot ARI.ta 1,. loultd ot ht OOl'Mirmtm wal. Tno sot.1t1e foOI' !ho r ooctM-*r 4IO by rruti;:iyr.;
the 9111t ll01l:lplll tll4to In Tlb'!I A3.1-3b'/ h "*8 of o r rnal'f eoob'lt ('2.*,e.a IO() Tht ncitil*oauouroe 
!!fr.$ are E P-CALC-C NP-1602 Page 1 6of 1 8 Rev is i on 0 Attachment 3 EVAL-RD-99-11 Bases I nformation Slllf!drn flodfi foe liiQh B1rot MM MA 131!lt'23 i.Q) CQC'C41 Wl!nl'll VRA 131G'23 i Oare loeslodM ltw:660fl devlllM (Rir.. M . .c} Ortt,'flc OOIO '1:tYI U!t llP* (l*. lllbc:wo tflO OOCk) wh k\ ttn CO'CualOi'\.
Th& itl't'n:ftbn bcb.-*h:opoia!ing O.C:l: Wbt 
'flt ln. tirQI I I* llll'Otll ttiree feel !IQ Pet t, h llf>PIW It rncdOl!rl M
* C)li'>Otir Tht Of 57.S t.
d c:ion\ll'll'llCSJI w
1 tr' anc 1 1&#xa3;9 
'Tliie efllctt.-o the uppor $ Ha ta the ht\fbt of upper ooobir.mll'!
l ll V a Ul* vol.tne d COf\Uintmt1I.
Ir Thi w Q C:. ll!CIMd by a volulTll t'dt> of 0.701 '&deg; :.oco.nt b Ol!ltt flO dOM from .i>>to '10 Pilr 3, VRA, 31 o it iocaect en tM inlllcle ot ht -...1. "'4'lli:tl gt.-o* h redlua of 57.Sft. ISOSHL.o.remo:!n.
Thohclghtot\IAA1lttnll01ntM tsOSHlO-PC tlO'-*(Ek!Y. 550 f'j elnc. "'9 fl"O:M l ert<<Ms frtJm Bev. <<oO ft. to :ht llOt) of h 4Cmt, Elw. 7M, (Ref'. M 6).
fqrc;t/\RMMl-' 
'ilW2"101 Cof'.lartnttll RtnQ* VRA 141Ci2*tO iSl2' IRt!i.
at:sri; N c<<YlahmM:
wt1 TN* Plitt M AA M eo-ilah:necrt 
""'' n tho c:c;na wa t. Oriy lht ll'l'lmN'$lon dl)M ffOM &#xa5;.<<hn V'll* ennlAllt bl ccinsldlnld In llH cclctJbdoll Tho tr)9 et#I& Wll Yt ?I tt1olded t:f ltlo cnne 'fo*a11noe It * ""'&deg; fMI fl\k'Jl P9c' 2. !Ha atll'llttr 
'* lnnor 8n:I ntd!l ct 44.G ano 51.6 t: P<< lhe 11 rr<<leMd .i an nM.11 Tht tltDd 
!!7 6 ft wic:1
* rupcellv<<y
* befcw EP-CALC-CNP-1602 Page 17 of18 Rev i sion 0 Attachment 3 EVAL-RD-99
-11 Bases Information ll'* awce fJlt be 1eaitd tr{ a r..so of O . ..Ot to a:CCM't lot onl)' ._ f l'!Yl'lllQiOn OoM
* llnlllH tpOClt en rd.io tf he wlun-. of ht .n11'1t spia ID ti.It d 
"'ce 3E.OS' 0.401). 119t1 rango ARY IO .. roctltd II fltva':ton 6 1 2' (Ro( AU).
eCcll'I: .....,...
llD0'-3 VRAt .. ,()'2410 la 16.7 ll The l*'Ctfla!O&
Cll IM! Wl'!M VRA14\M410 ltUICl.'lled btlow. %Qf t ltf* 15*7 ft t g 11&.1 Jt ThelVtcre tho heq& a l VR.t.t*U0.'2410., ._ '90SHIJ).PC model b IJ'lfl'I bt1ow H191t
* 15U ft
* 0 Oe14
* 13 8 It Per AlisumpbC<>
: 3. \IRA 1 .. 1 0.'2*'10
* loe.atbd en 11e 11'1116d6 eone,, ...... w!littl ;i'fe* u ot 61.6 It. h l'IO I SOSKl.C*PC AJA. R,_b 111d Colldv.,.,.
: n. ruula eite limna'!MO In T ab!i: A3.4*t imM.
Co!jln!!Jj0! 
!1!11 h RarM/llW DoM r l1H CMe Oc4.e Rafi9. Rh:r =--i L oe.A 3.128ES I VRAIS1<ll2310
' "*&#x17d;ES Fut!ROOGap VRAt4 1 0.'24\0 3.12'!E<1 
\/RA I 3 Hl'23 \0 *U5se.t ()peo'OdollS l VRA t 21eE1 t 1 41E i EP-CALC-CNP-1602 Page 18 of 18 Revision 0 I}}