ML20140D576

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Rev 0 to Haddam Neck - Radiological Consequences from Resin Accident
ML20140D576
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 05/30/1997
From: Crandall R, Fliak D, Landry L
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20140D536 List:
References
CYRESIN-01578-R, CYRESIN-01578-RY-R00, CYRESIN-1578-R, CYRESIN-1578-RY-R, NUDOCS 9706100419
Download: ML20140D576 (22)
v • d • e


Text

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Haddam Neck - Radiological Consequences From a Resin Accident TITLE CYRESIN-01578-RY 0

NA CALCULATION #

REV#

Vendor Calc #

System NA Structure _ NA Component NA f Executive Summary l

~

This calculation evaluates the potential site boundary dose from an accident involving a decontamination resin liner. This accide.at is considered the bounding radiological accident for decommissioning activities. An asstuned release of 1% of the activity in the hner is based cn a fire, but is choscn to bound the relcase fraction for any resin hner accident such as a drop.

The dose was calculated using two methods. One method used NRC approved dose conversion factors from Regulatory Guide 1.109 as this calculation will be used as a FSAR Chapter 15 DBA. ' Die second method used EPA 400 dose factors as this calculation will be used to support Emergency Plan changes.

The resulting dose to the total body at the site boundary was 0.43 REM using method I and 0.% REM using sucthod 2.

Both results are within acceptable limits.

Does this calculation:

1.

Support a DCR, MMOD, an todependent review method for a DCR,or confirm test results for Yes CNo @

an installed DCR? If yes, indicate the DCR, MMOD number and/or Test Procedure number.

2.

Support independent analysis? Ifyes, indicate the proccdure, work control or other reference Yes ONo E it supports.

3.

Revise, supersede, or void existing calculations? Ifyes, indicate the calculation nutnber sad Yes ONo @

revisions.

4.

Involve OA or OA related systerns components or structurcs?

Yes C No 5 -

Y Impact the Unit licensing basis, including technical bpecifications, FSAR, procedures or Yes @No 7 licensing commitments? Ifves identify appropriate change documents FSAR Approvals (Prmt/ Signature).__

^ ' ' * ' ' "

L. J. Luony

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  • r.u.n Interdiscipline Reviewer:

Date-Discipline:

Interdiscipline Resiewer Date:

Dgpline:

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CYRESIN-01578-RY, Rev 0 Page 2 Table of Contents l

1. P u rp o s e.................................................. 5
2. Summary o Results.......................................

5

3. References...............................................

7 Assumptions..............................................

8 4.

5. Method of Calculation....................................,9
6. Body of Calculation.....................................

13

7. Design Verification.....................................

17

8. Attachments and Forms........................

.......... 18 (Total Number of Pages in Calculation 22)

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CYRESIN-01578-RY, Rev 0 Page 3 List of Tables Table 1 - Assumptions 4

Table 2 - Resin Activity 14 Table 3 - Site Boundary Dose (DBA Analysis) is Table 4 - Site Boundary Dose (EP Analysis) 16 l

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CYRESIN-01578-RY, Rev 0 Page 4 i

l Table 1 - Assumptions

]

Assumotions Basis

1) Resin activity CY Calc # RPE97-01573-R-Y t

r Decontamination Resin i

4 Loading 4/14/97

2) Maximum fraction released (based on fire as worst case) = 1%

Reference 1 i

3) Dose conversion factors (DBA Analysis)

Reference 2 Dose conversion factors (EP Analysis)

Reference 5 i

4) X/Q @ site beundary = 1.08 E-03 sec/m*

Reference 4 i

l

5) Breathing rate (DBA Analysis) = 3.47E-04 m /sec Reference 7 3

I Breathing rate (EP Analysis) = 3.33E-04 m /sec Reference 5 l

a

6) Lung weighting factor = 0.12 Reference 8 Bone weighting factor = 0.12 Reference 8 l

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CYRESIN-01578-RY, Rev 0 Page 5 l

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1.

Purcose The purpose of this calculation is to determine the Site Boundary (SB) Dose from an accidental resin liner fire.

The worst case credible event would be a fire releasing ik of the contents of a resin liner (Reference 1).

This event would 1

bound other mishaps such as a liner drop.

Two methods were used to determine the dose:

Method 1 is used for Design Basis Accident (DBA) analysis; Method 2 is

]

used for Emergency Planning (EP) analysis.

2.

Summary of Results The results of the calculation for site boundary doses are:

Committed Effective Dose Equivalent = 4.33 E-01 rem (DBA Analysis)

Total Effective Dose Equivalent = 9.60 E-01 rem (EP Analysis)

{

Since this event is not an accident in the Standard Review Plan, the site boundary dose was determined using both the NRC recommended dose conversion factors from Reg Guide 1.109 (for inhalation) and from EPA 400 (for immersion, inhalation and ground deposition).

Although the site boundary dose is higher using the EP analysis method, both methods are less l

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CYRESIN-01578-RY, Rev 0 Page 6 j

than the 1 rcm Protective Action Guide (PAG) for che immediate plume dose consequences.

Additiona'ly, both results are a small fraction of the 10CFR100 limit of 25 rem for the whole body.

i Reg Guide 1.109 dose tactors were used for the consequences l

i from inhalation of plume activity.

Since the nuclides released are all in particulate form, several with high dose conversion factors for internal dose from inhalation, the plume shine dose was assumed to be insignificant compared to the inhalation dose and hence is not calculated.

This is confirmed ' by Table 4 (EP Analysis, Method 2),

where the j

immersion dose is less than 1% of the inhalation dose.

This I

calculated dose was determined for the inhalation pathway t

during plume passage and represents a

50-year dose commitment.

I i

The EPA 400 dose conversion factors were used for the immersion, inhalation, and ground deposition pathways to determine the total dose.

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CYRESIN-01570-RY, Rev 0 Page 7

3. References
1) NUREG 0782, Environmental Impact Statement on 10CFR61,

" Licensing Requirements for Land Disposal of Radioactive Waste", September 1981.

2) Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Reculatory Guide 1.109, Rev. 1, US Nuclear Regulatory Commission, October 1977,
3) NUREG 0172, Age-Specific Radiation Dose Commitment Factors November, 1977.

i

4) Santovasi, J.

A., Chi /Q's at Site Boundaries and LPZ (4345m) i for Release from Outside Face of Containment and Containment Vent Stack, 93t. 1 Calc. # XXXXX-30-P_S, Rev.

O, September 24, 1981.

S) EPA 400-R-92-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, US EPA, 1991.

6) ICRP 30, Limits for Intakes of Radionuclides by Workers, July 1978.
7) Reoulatory Guide 1.4, Assumptions used for Evaluating the Potential Radiological Consequences of na Accident for Pressurized Water Reactors, USNRC, June 1974
8) LCRP 26, Recommendations of the International Commission on Radiological Protection, January 1997.

I 1

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l CYRESIN-01578-RY, Rev 0 Page 8 l

4.

Assumotions The accident involving resin that would have the highest release of radioactivity t'a o determined to be et fire, one l

recin liner in assumed to burn and relcacc 1% of the contents to the environment.

Although there is a range of values for release fractions derived from empirical studies, 1% was conservatively chosen using Reference 1.

The 1% release fraction was determined to be appropriate for radioactive waste with a flammability index of 2 which is materials that will burn if heat is applied but do not otherwise support burning.

J The worst case resin activity was determined to be that resulting from a proposed full system decontamination.

The curies in a liner were rnaximized to the level that shipping and burial requirements would allow.

The activity of each nuclide in the resin liner are given in Table 2.

The 1%

release from a fire is assumed to bound the release fraction from other events such as a drop.

The other assumptions used are listed in Table 1.

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CYRESIN-01578-RY, Rev 0 Page 9

5. Method of Calculation i

l Method 1 (DBA Analysis)

I l

The Site Boundary (SB) dose will be calculated using the j

following equations:

CDE = Ei(AtxF x DCF,o x BR x X/Qss)

(Equation 1) b r

i where:

CDE. - Committed Dose Equivalent at the site boundary for organ *o" (rem) 1 activity in resin liner (C1)

A

=

F, = release fraction DCF,.

inhalation dose conversion factor S

=

for organ "o" a:.-l nuclide "i" (rem /Ci) r X/0

= atmospheric dispersion coefficient 33 at the SB (sec/m')

BR = breathing. rate (m'/sec)

CEDE = I.CDE, x w.

(Equation 2) where CEDE = Committed effective dose equivalent (rem) i I

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CYRESIN-01578-RY, Rev 0 Page 10 w, - weighting factor organ 'o" t

i Note: A review of the nuclide mix, activities, and l

organ dose factors indicated only the lung and bone doses will be significant. Therefore, only the lung and bone were considered in determining i

i

'The weighting factors for bone and lung i

CEDE.

1 l

were taken from ICRP 26 (Ref 8).

i Total Effective Dose Equivalent = CEDE + DDE (Equation 3) where CEDE = Committed effective dose equivalent l

j DDE = Deep dose equivalent from immersion in l

a semi-infinite cloud from the plume pathway (excluding ground deposition).

Since the source term is all particulates, many with high inhalation dose conversion factors, DDE'is assumed l

i to be negligible; and therefore, Total dose equivalent is approximated by CEDE, l

Method 2 (EP Analysis)_

)

1 l

The Site Boundary (SB) dose will be calculated using the following equations:

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CYRESIN-01578-RY, Rev 0 Page 11 CEDE - L (A1 x F, x DCFinhalation X X/Qsa) /3600 (Equation 4) j where:

CEDB = committed effective dose equivalent for inhalation (rem)

{

A activity in resin liner (Ci) i =

F, = release fraction DCF

= inhalation dutse conversion inn.1, tie.

factor for nuclide

  • 1" (rem per pCi cm hr) x /Qsa atmospheric dispersion coefficient i

=

at the SB (sec/m')

i 3600 sec = hr t

DDEteersion - L (At x Fr x DCF

.,,ico x X/Ose) /3600 (Equation 5) l t

where:

DDE = Deep dose equivalent for the plume immersion (rem) t DCF -raim = plume immersion dose conversion 1

t factor (rem per pCl cm*' hr)

DDE.pc.icteo = L (A x F, x DCF a

1 deposition X %/Osa)/3600 (Equation 6) where:

DDE - Deep dose equivalent for the ground deposition (rem) i

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CYRESIN-01578-RY, Rev 0 Page 12 l

DCFa pe,ieten = deposition dose conversion factor (rem per pCi cm hr)

Total Effective Dose Equivalent -

CEDE + DDE o.,, ten + DDBa.po,teien (Equation 6) i f

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==.

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CYRESIN-01578-RY, Rev D Page 13 i

I 6.

Body of Calculation l

l The equations from Section 5 were used in Microsoft Excel 5.0c spreadsheets and are shown in Tables 2, 3&4.

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CYRESIN-01578-RY, Rev 0 Page 14 Table 2 - Resin Activity lootope Activity (mCl)

Curies Co60 6.4074E+04 6.4074E+01 Cr51 2.7628E+03 2.7628E+00 Mn$4 2.2266E+02 2.2265E-01 Co 58 1.8084E+03 1.8084E+00 H3 1.0102E+00 1.0102E 03 C 14 6.0473E+01 8.0473E-02 Nf63 2.2296E+06 2.2296E+02 Fo SS 1.439CC+0G 1.4396E+02 Am 241 2.8799E+02 2.6799E41 1

Cm 242 1.2001E+01 1.2001E 02 Cm 243 1.4161E+02 1.4161E 01 Cm 244 1.4161E+02 1.4161E-01 i

Np 237 8.6759E-02 8.8759E 05 Pu 238 4.4883E+01 4.4883E.02 Pu 239 2.7678E+01 2.7878E-02 Pu 240 2.7678E+01 2.7678E 02 Pu 241 1.0338E+03 1.0338E+00 Pu 242 1.6889E-01 1.6889E44 Fe 69 5.0530E+03 5.0530E+00 Co 57 1.9851E+02 1.9661E 01 Ni 59 2.3675E+03 2.3675E+00 Zn 65 1.2728E+03 1.2728E+00 Sr 89 1.3668E+01 1.3668E-02 Sr 90 1.2064E+01 1.2064E-02 Zr 95 3.0573E+03 3.0673E+00 Nb 94 8.$704E+00 8.5704E43 Nb 95 6.4174E+02 5.4174E-01 Tc 99 3.9123E+00 3.9123E-03 Ru 103 9.2003E+03 9.2003E+00 Ru 106 4.0315E+03 4.0315E+00 Ag 110m 5.6080E+02 5.6080E-01

$b 124 1.2449E+03 1.2449E+00 Sb 125 1.1999E+03 1.1999E+00 1 129 4.7057E+00 4.7057E-03 Cs 134 2.5858E+03 2.586PE+00 Cs 137 1.2815E+03 1.2815E+00 Ce 141 1.6228E+04 1.6228E+01 Co 144 1.8988E+03 1.8986E+00 Total 4.8831E+06 4.8831E+02 i

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Table 3 - Site Boundan Dose Results (DBA Analysis) l 2

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Theidore, only the lung and imne were consedered in detemunmg CEDE.

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CYRESIN-01578-RY, Rev 0 Page 16

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4s Table 4 - Site Boundary Dose Results (EP Analysis) 5

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S Pe 86 140eE+s2 1440E*0s l osE481.30E42 12eE*e3 E7eE41 EMeE4e L3e2E43 3787Ebe7 t.382E43

  • z 4es 249 2Ame581 2Ae8E43 TARE 46 t. tee +49 EJeE+0S 1.2eE*02 WJ 44E4e L201EC1 eA44E4e (26t E41 Can 242 1J00E42 1.200E44 1 AGE 43 Lese 42 2.iOE*0F 37CE*00 2(18E42 7.600E44 1332E-10 7.5stE44 Z

Can 343 141eE49 f.416E43 1 AGE 43 7JeE+01 L7eE+se Se3E+02 1101E45 1A72E41 2Ae4E4F 1AT2E41 2

  • "~

Cin2e4 1AssE41 1AteE43 1 AGE 43 430E42 temE+0S 130E+ee 2A30E 11 1.274E41 1402E4e t274E4s C

Np 237 SAF6E46 SA79E47 00eE44 1.3eE+et SABE*ee 1JeE*e2 324E-42 1Ae2E44 13e4E41 1.E52E44 Pu 23e 4AgeE42 4AteE44 1 AGE 4e SAGE 42 470E*00 3 AGE *0s eJ32E.t2 632eE42 45FSE-10 tt39E42 Pu 23e 2.?seE42 2.75eE44 TJeE43 47eE42 5.20E*00 1.60E*ee 3.se3E-12 4 318E.02 1AseE4e 4.3 tee 42 r

Pg 380 2.74eE42 2.768544 100E43 4.eeE42 L3eE*ee 3.2eE+0e 4AmeE42 4.3 tee 42 2.867E.94 4J10E42

D Pts 241 1A34E+es te34542 1.ceE43 0 00E*00 S.eEE *et s.00E*eC-0390E800 3A7e642 8.eseE*ee S e70E42 Pe 242 1A80644 1840E40 EAeE43 42eE42 te0E+es 2JEE*et 2.12tE44 2A43E44 1.380E 12 2 483E44 2

Fe se 5.eS$E*00 5.063E42 1 AGE 43 7AeE*e2 000E*04 (20E+03 1.05tE45 2.72eE44 S.Se7E4e 3AttE44 Co GF G geSE49 1.000E43 1AeE43 ele m!a nfo nfo nie sera nia sel se 2.3s7E+0e 2As7L42 E.00E43 nas s>fe ape sWe n8e sta sede e

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2. tee *e3 1JesE4e S.te4E45 0 0 tee 4e te10E44 C

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Zres 3.DSTE*0s 105F582 LOSE 4B &3eE*e2 2 AGE +44 2 8 E+03 3.

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hb ee SA17E41 SA1FE43 theE44 4eeE+et Ft0E+e3

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fc 00 S e12E 03 3 012E46 1AeE43 EteE44 153E*04 2.00Eee3 3 62tE.96 1174E47 2A34E4s 1.48tE47 C

ftules 13e4E*00 R200E42 1 CeE4s 2ASE*02 teeE*04 1 tee *03 F.72eE46 3 03eE44 6AeE45 3.43eE44 Ra teo 4A32E+es 4A33642 toeE4E t20E+C2 S.7EE*e6 E3eE+e2 tAHE46 &seeE45 1A04E45 S.ge6E43 Ag 19euri SAesE41 SAceE43 (AeEAR (SOE*03 GAEE*e4 1.2eE*et 2Ae?E4s 1A15E44 2.010E47 1A44E44 Ste 124 1246E*to 12e5E42 1;BGE431. tee +03 200E+04 GAGE *e3 41(eE4s 112eE44 2.SetE46 1415E44 Sb 126 1J0eE*00 9.200E42 1 ASE43 ges nfa man mas efe ese ets 812e 4784E43 4JesE46 SAeE M 4 ACE *e0

2. tee *e5 E7eE+02 SJ78E41 2 0$eE45 122eE49 2 SFTE4e CetM 2JeeE*es 2AstE42 tJeEM e.10E*C2 EASE *e4 e3eE*e3 7.eesE.06 AS44E44 4 810E45 4400E44 Cs 337 12stE*40 1J91E42 1ABE42 3.59E*e2 300Esee FASE*e3 13SE45 1A41F.44 e.227E4s tes?E44 Ce 141 9.623E*ei SA23E48 1ASE42 4 AGE *e1 S.ieE*04 3.30E e2 2.142Eas $3eeE44 teerE46 0 63rE44
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3.30aE44 s.5eeE49 2A$1E43{ 9.044E-01 I

NAY-30-8I FK1 15:14 NUCLERK PUEL ENUiNthKING PRX NV BbV 852 49UU l'. 10 l

r i

l Cat. 1 Calc. #

l CYRESIN-01578-RY, Rev 0 Page 17 7.

Desian Verification No design inputs are being created or modified.

~

= _ -

tiAY-30-9( FR1 lb'1b NUCLERK FUEL ENGINEERING W HO M O E E 0 hW i

Cat. 1 Calc. #

CYRESIN-01578-RY, Rev 0 Page 18

8. Attachments and Forms Reviewer's Comments Con:ments from Dwight Vann
1. Basis for 1% release fraction.

Incorporated in section IV) Assumptions.

2. EPA PAG not provided.

Incorporated in section II) Summary of Results.

3. Justify why plume shine is insignificant.

Plume shine dose was not calculated but would be i

insignificant compared to the inhalation dose. Wording added to justify this assumption. Halogens are not present due to decay.

4. Delete paragraph discussing long-term doses from ground shine.
Deleted, t
5. Is AAAxx a valid calculation #?

This was not a valid reference # and was modified.

6. Replace NREG with NUREG on reference page.

j i

Incorporated.

7. Use EPA 400 DCF factors.

1 Reg Guide 1.109 values are used for all other Design Basis Accident Calculations and want to maintain consistency.

8. Two Table 2s?

Tablen renembered.

9. Where is table 3?

i l

l

nay-30-9( FR1 15:1b N00 LEAR F0EL EHg1HEER1HG FAX HO. 860 832 4900 P. 20 Cat. 1 Calc. #

CYRESIN-01578-RY, Rev 0 Page 19 Tables renumbered.

10. Spreadsheet should whow DCFs used.

Incorporated in Table 3.

11. Memo from Richard McGrath is missing.

The memo was not a valid reference and was eliminated.

Ccuments from Tom Turisco l

1. Dose seems reasonable based on comparison to YRC-1014.
2. Basis for it should be explained in more detail.

Incorporated in seccion IV) Assumptions.

3. All components of TEDE are not calculated and incorrect DCFs.

TEDE is estimated from CEDE and DCFs were from Reg Guide i

1.109 which is used for design basis calculations.

4. Reference 5 not used in calculation, t

i Safety Guide 24 reference was eliminated.

5. Reference 6 not listed in the reference section.

Added reference 6 in references section.

6. References 1 & 4 appear to be references to drafts.-

Reference 1 was not valid and was eliminated, reference 4 is a valid reference calculation.

Comments from Dan McDavitt 1

l 1.

Reduce conservatisms such that the resulting dose is a small fraction of the EPA PAGs to help justify " Alert" as the highest Emergency Plan Classification.

l

=

--mm

f1AY-30-9I FRI lb:1b NUOLEAR FUEL ENGINEERING FAX NO. 660 832 4900 P. 21 i

l l

l Cat. 1 Calc. #

CYRESIN-01578-RY, Rev 0 Page 20 l

The calculated ascomptions are not overly conservative.

Certain assumptions such as x/0, breathing rate and dose factors are standard industry practice and cannot be changed.

The assumed resin activity will only be achieved through tight decontamination project controls and will result in many liners as it is and hence cannot be reduced.

The fraction released is a reasonable compromise.

A recent Sandia report used 100% released from a resin fire.

Yankee Atomic used 25% released for a component drop.

These values are overly conservative. One percent represents a reasonable upper bound.

The cask drop accident also results in doses approximately 50% of the EPA PAGs.

Therefore reducing the resin release results will not solve the problem.

Based on these two points, no change in assumptions is being made.

Comments from Dale Flick I

1.

A separate calculation for the DBA Analysis (Method 1) was i

performed (enclosed).

The assumption of limiting the dose to only the bone and lung organs is reasonable because the minimum percent these two can be of the total for all Reg Guide 1.109 and NUREG-0172 DCF organs is approximately 80%.

2.

In Table 3,

the following DCF's were from NUREG-0172 (and

{

nnot Reg Guide 1.109):

Am-241, Cm-242, Cm-243, Cm-244, Np-237, Pu-230, Pu-239, Pu-240, Pu-241, Pu-242, Co-57, Ni-59 Tc-99, Sb-124 and Sb-125.

Also, TC-99 DCF's are actually the l

[

. ~... _ _ _ _ - -.,.. _. _ _ _ _

. _ _. _ ~..

flHY-6U-8f PKI IB;1b i1UULthX PUtL tNUINthKINU PHA NU. bbU 032 48UU

r. 2d Cat. 1 Calc. #

CYRESIN-01578-RY, Rev 0 Page 21 TC-99m values from NUREG-0172;

however, this does not significantly effect the overall organ doses.

l 1

l I

i l

Revievrer's Vertncatkut Calcarlation for DE A #nalyste (Calc CYRES3dait73M, Rev 6)

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0 129E-0? 7 73E48 2 9"E&

t esEm 4 30EM De 54 222 ES295 2 227E*IE)

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4 9eE47 2 59E-07 0

0 1 f tE04 131EM 0

154E-DE 17tE-06 0

0 788E44 9 DIEM H3 S C10tS 1010E+07 0

158E47 I SPE47 15E 47 198E47 15EM 15aF47 0

5 !aiE-10 5 98E-10 5 9eE.10 59E10 590E-1C S E8E-10 E

C 34 80 4728 6 047E*0m 2 27Em 4 2*EC 4 2tF47 42E47 4 2EEN 4 2E47 4 2GE47 114507 915E-08 9 85E 08 e 66E48 9 e'E On s E 41 9 66E48 p

te 63 272962 805 2 23DE+12 5 43E45 3 E1EM 9 BTE-OR 0

0 2 2EE 1 tr7E 48 4.51E42 3 38E43 15'E 43 0

0 t eeE-02 14Ne rT-Te 55 143 epi 9 995 1440E*12 107E-06 2 f2EM 4 50E47 0

0 9 DEOS 7 54E47 9 86E43 1 14E-03 2 SEE44 0

0 4 arE-03 4 07E44

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" Mi 241 257 99383 2 8FE*04 1C1E*00 35eE41 671E42 O

S O4E-01 60Fr42 e sDEe 101E *00 3 t"16 01 8 74E42 0

508E-01 609E42 46264

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4 4BE-03 3S2'[42 4 91Em 6eeE44 619E44 4 43E45 0

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" C>t 244 141 ED9Re4 14eE *09 59]E41 2 54E41 3 51E 42 0

164E41 606E42 4 8 REM 313E41 t N41 I BSE 02 0

8 7tE-07 3 2:E-02 2 48EG r-

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0

$ 90E41 &22542 4 92E4 54E 04 4PEm 2 235G 0

1 GEE 44 1.70E46 150EG

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4 HMEC 3 ore 42 7 60Ee 2

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0 127544 2 36E45 2 78IEE 6 57E45 2 SDE4E O

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0 344Ee 2 92E45 c:

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0 175344 4 37E45 195E45 0

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0 8 teems 2 24Em Sr 93 12 G53915 12DEE*M 124E42 0

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0 0

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0 Nt: 95 541 TM 5 4t TE*09 17EEM 977507 5 26E47 0

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8 58E@ 14eEm 1 1tE47 Fu 103 9200 31 9 200E*10 19'E47 0

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cr Pw 106 433152 4 032E+10, 8 64E46 0

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2.4rE-06 S 7tE44 3 78E-06 2 84E4 2fBE45 15EE48 0

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