SNRC-2165, Submits Technical Info on Biological Shield Wall Blocks to Be Surveyed
| ML20029C711 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 04/22/1994 |
| From: | Bortz A LONG ISLAND POWER AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LSNRC-2165, NUDOCS 9404260386 | |
| Download: ML20029C711 (13) | |
Text
-
Long Shorchum Nuclear Power Station -
.i Island P.O. Box 628 Power North Country Road iuthority Wading River, N.Y.11792 1
LSNRC-2165 APR 3 21994 U,S. Nuclear Regulatory Commission Dacument Control Desk Washin0 ton, DC 20555 Attn: C. L. Pitti0lio Request for Modification of Facility Release Criteria; Apr%ation to Low Ener0y Beta Emitters and Electron Capture Nuclides Shoreham Nuclear Power Station - Unit 1 Dock' 50-322 Ref:
(1)
Long Island Power Authority Letter LSNRC-2133, dated January 10, 1994; subjact: Shoreham Decommissioning Project Termination Survey Plan - Revision 2 (2)
Telecon between D.
Fauver (NMSS) and S.
Schoenwiesner, F.
Potschauer, M.
Tucker (LIPA) dated April 12, 1994; subject:
Termination Survey Concerns for Bioshield Blocks and Limitations on Post-License Termination Activities Ladies & Gentlemen:
As provided by Reference 1, present plans for performing the termination survey of the Shoreham facility include certain provision to account for the presence of isotopes which are not typically detected with field survey instruments. Specifically, a scaling factor of 1.2 has been developed from samples of typical corrosion product deposits at the facility, to account for the potential presence of undetected Iron-55. As
' described in the Termination' Survey Plan, this factor is applied to all termination survey measurements.where results are statistically greater than background.
9404260386 940422
{DR ADOCK 05000322 I
I-PDR
4 i
LSNRC-2165
.Page 2 of 3 As a result of continuing decommissioning activities,it has become necessary for LIPA to include surveys of blocks containing patentially activated concrete and steel from the biological shield wall in the final termination survey. In approaching the block surveys, LIPA has determined that the previously described scalin0 actor may not f
account for all isotopes present in the concrete or steel, nor will that factor provide the correct adjustment for the calculated ratios of the undetected isotopes to the detectable isotopes. This matter was discussed with the NRC staff, as noted in Reference 2. During the discussion it was recognized that application of an increased scalin0 actor to account for the undetected presence of both iron-55 and tritium (H-3) f in neutron activated biological shield wall materials would, under the limitations of Regulatory Guide 1.86 as presently implemented in the Shoreham Decommissioning Project Termination Survey Plan, severely limit LIPA's options regardin0 the proper L position of this or any similar materials. provides technicalinformation on the biologicalshield wall blocks which are to be surveyed. From this information it can be seen that if the present release criteria for release for unrestricted use is applied to the expected survay results from this concrete, the concrete will not meet the criteria solely because of the high iron-55 and tritium scaling factors. This would thus necessitate the shipment and burial of the concrete, at a cost of approximately $1,000,000, without a clear benefit as evidenced by the absence of any appreciable dose rate or health risk from the
safety of the public than other beta-gamma emittin0 sotopes which are appropriately i
4 restricted by the limitations imposed by Regulatory Guide 1.86, Table 1.
LIPA understands that the NRC is considerin0 to address this issue for certain other decommissionin0 projects by revising the allowable levels of residual contamination which result from certain low energy beta Gamma emitters such as the Iron 55 and tritium calculated to be present at the Shoreham facility. LIPA therefore requests the NRC to consider application of these revised release critoria to the Shoreham decommissioning effort.
Althou0h the precise release critoria have yet to be 2
established, LIPA understands the current average limit of 5,000 dpm/100 cm for heta-gamma emitters could be increased to love s of between 100,000 to 150,000 dpm/100 cm' for weak beta emitters or electron capture nuclides such as tritium and f ron-5 5. Were such increased limits to be appli3d to the surveys of the activated concrete and steel at Shoreham,in the manner d.iscribed by draft NUREG/CR 5849, Appendix A, it is likely the biological shield wall blocks would meet the release criteria for unrestricted use and avoid the tremendous cost of shipment and burial. The environmentalimpacts and industrial safety risks associated with the handling of these j
blocks would also be avoided.
l 9
u u
LSNRC-2165
.Page 3 of 3 Should the above request for modification of the facility release criteria be granted, LIPA intends to apply the revised guideline values only to survey units where the most probable source of potential residual contamination is neutron activated materials.
I These survey areas include the biological shield wall blocks themselves and other ueas where residual contamination from block cutting and handling may exist. It may also include surveys of areas containing activated metal or metal residues within the i
plant dryweli and in the Dry Cutting Station. The remainder of the facility will continue to be surveyed and reported in the manner described in Reference 1, utilizing i
the scaling factor for Iron-55 which is appropriate for residual contamination resulting from the deposition of corrosion product materials.
Please do not hesitate to contact me if you have any questions or require any additionalinformation in this matter.
Very truly yours, c
A.J.
ry Resident Manager cc:
D. Fauver R. Nimitz R. Bernero, Director Office of Nuclear Material Safety and Safeguards bec:
C. Giacomazzo Chairman IRP S. schoenwiesner J.
Brons F.
Petschauer R.
Bonnifield T. carvey W. Merritt L.F.
Britt S.
Skorupski S. Maloney E.
Pierpont l
R. Petrone D.
Filipowicz l
T.S. Cardile M. Tucker l
J.
Foley LRCD File R.
Pauly Records Management
[,
TERMINATION SURVEY MEASUREMENTS WHERE HIGH FRACTIONS OF
.l HARD-TO-MEASURE NUCLIDES MAY BE PRESENT INTRODUCTION The Shoreham Decommissioning Termination Survey Plan indicates that the major source of residual contamination (from licensed facility operations) is activated corrosion products deposited in piping systems. These deposits were characterized as predominantly Co-60 and Fe 55 with an Fe-55:Co-60 ratio of 0.19, adjusted for radioactive decay to June,1994.
Application of this ratio (rounded to 0.2) leads to an adjustment factor of 1.2 applied to measurements of surface beta-gamma activity (direct and removable) to account for the unmeasured fraction (Fe-55) on gross activity measurements determined to be "above background".
However,in some instances the potential source of contamination may be of different origin than piping system corrosion product deposits. For example, portions of the Reactor Biological Shield (poured concrete and stec!) which were neutron activated remain in the facility.
Shoreham Site Characterization results indicate that the isotopic composition and ratios of hard-to-detect species to Co-60, e.g., Fe-55:Co-60 for these materials are significantly different from plant corrosion product deposits. The ratios of hard-to-measure species to Co-60 concentration are calculated to be as high as 25 to 1. Given these circumstances, two options are identified: 1) all bioshield wall materiali, with " detectable" activity are disposed of as radioactive waste as they do not meet the release criteria when material specific adjustment f actors are applied to direct surface activity measurements; or, 2) special guideline values are applied to termination survey measurements on potentially cnntaminated materials with large uactions of hard-to-measure nuclides.
CHARACTERIZATION OF NEUTRON IRRADIATED STEEL AND CONCRETE The Bioshield wall materials of concern are blocks produced by diamond wire sawing to facilitate dismantling of the wall and dhposal of the wall region where calculations have shown that the 5 R/hr gamma exposure rate mioase criterion is not satisfied. Two layers of blocks from the upper portions of the Bioshield wall which were removed to gain access to the most highly activated portions remain on site. These upper portions are identified as the "C" and "D" rings of the wall Gamma dose rate measurements indicate that all the C and D rint.ocks satisfy the 5 pR/hr criterion. Figure 1 shows a view of a typical block, comprised of aured concrete with carbon steel plates lining the inner and outer surfaces of the former.
Bioshield wall structure. The isotopic composition of these materials as derived from neutron activation calculations is summarized in Table 1.
i s
1 i
'l
4 Table 1 Radionuclide Composition of Neutron irradiated Bioshield Wall Materials Material Nuclide Ratio to Fraction Co-60"8 of total
Co-60 1
0.03 Steel Fe-55 24.7 0.96 Co-60 1
0.04 l
l Table 1 Notes:
(1)
Ratio of nuclide to Co-60 for specified material.
(2)
Fraction of total activity in specified material.
l These results tre obtained from Shoreham Site Characterization Report data corrected for roJioactivo deca y and normalized to the concrete and steel mass in the Bioshield wall (See Appendix 1, April 11,1994 Memorandum from N. Lizzo to M. Tucker). Minor constituents I
identified in the activation analysis, such as C-14, Ni-59, Ni-63, and Mn-54 are neglected as.
-I together they comprise less than one per cent of the total activity and may have already been
)
included as part of the Co-60 equivalent activity estimate / survey.
l RESULTS OF PRELIMINARY TERMINATION SURVEY MEASUREMENTS I
l Direct surface activity measurements fro n exposed steel and concrete surfaces were taken on 25 blocks from the C and D rings, on or about April 11,1994. Each measurement was converted to dpm/100 cm' using the detector of ficiency developed for the Termination Survey J
and a background valua obtained for the detector and materialin accordance with Termination j
Survey Procedures.
From these measurements, two populations are obtained, one comprising measurements on I
steel surfaces (50 measurements) and one of measurements on concrete surfaces (38 measurements). It is concluded from a review of these data and supporting investigations, that no detectable activity is present on concrete surfaces, but detectable surface activity is present in the inner steelliners on several of the blocks. The results of the measurements on steel and concrete are displayed graphically in Figures 2 and 3. In these figures, the calculated results in dpm/100 cm are plotted vs the survey location code.
2 A.i
AttachmGnt 1 The criticallevel ' is also plotted to identify those measurements which are considered to be above the background value, indicating the presence of detectable activity. Figure 2, the steel I
. measurement graph, shows that several rneasurements exceed the criticallevel. Figure 3, for the concrete measurements, shows no evidence of detectable activity. The measurement data and the calculated activity results for each of the steel measurements is shnwn in Table 2.
' Qualitative gamma spectroscopy measurements taken with a portable Nal scintillator on exposed surfaces confirm the presence of Co-60 activity in the steelliners on two of four blocks evaluated by this method. Gamma spectroscopy measurements at four concrete surface locations with the highest direct measurernent results showed no detectable Co-60.
The measurements described above were all treated according to the current termination survey data evaluation procedure, whereby all measurements above the critical level were multiplied by the present factor of 1.2 to account for Fe-55. Under this treatment, none of the 2
measurements exceed the guideline value of 5,000 dpm/100 cm. However, if the steel measurements above the criticat ievel were to be adjusted based upon the Fe-55:Co-60 ratio in Table 1,i.e., multiplied by a f actor of 25.7 in Table 4,16 of the 50 measurements would 2
ta above the current 15000 dpm/100 cm elevated area guideline value. The 16 measurement 2
values when so adjusted, range from 15700 up to 34,000 dpm/100 cm.The resulting sample 2
2 average for the 50 measurements is 7980 dpm/100 cm, well above the 5000 dpm/100 cm guideline value.
in the Shoreham Decommissioning Termination Survey Plan, the critical level for surface activity measurements is defined as... the upper confidence limit, at the 95 %
confidence level of the observed not count distribution whose mean value is zero 2
(converted to dpm/100 cm ). It is calculated as:
L = 1.96lSl+Sl
^
E(100) where:
i L. = the Criticallevel, used to identify measurements most likely to be "above" background.
S = the counting error in the measurement, S = the counting error associated with the assigned background, E = detector efficiency in counts por disintegration, and 2
A = area of detector sensitive region (cm ), and 1.96 = 97 percentile value of a one-tailed normal distribution. !
Attachmsnt 1 DISPOSAL COST ESTIMATE FOR BIOSHIELD RING BLOCKS If required to be disposed of as radioactive waste, each block containing detectable activity will cost $21,000 to dispose of, exclusive of transportation costs which are about $5,000 per shipment. The cost estimate is as follows: burial cost of $300 per cubic foot and the volume of a typical block is 70 cubic feet. As an upper limit estimate for C and D ring disposal costs, it is assumed that all 25 blocks are found to contain detectable Co-60 activity and are disposed of as radioactive waste. The total cost is approximately $ 600,000, assuming two blocks per shipment.
After removal of the most highly activated portions of the Bioshield wall, the E and F rings, the remaining Bioshield wall will be evaluated in place. If the G ring is found to contain detectable Co-60, this material may also have to be disposed of as radioactive waste under the current release criteria guideline values. This adds approximately $ 300,000 to the estimated burial cost.
In addition, this extra volume may cause LIPA to incur a thirty percent penalty factor at the burial site if our present space allocation is exceeded.
APPLICATION OF REVISED GUIDELINE VALUES An alternative has been proposed whereby special release criteria guideline values are utilized which take into account the relative biological risk posed by the various hard-to measure radionuclidos. To illustrate, gt oss activity guideline values are developed for steel and concrete materials of radioactivity composition shown in Table 1. The example used here utilizes 2
individual nuclide guideline values of 150,000 dpm/100 cm for the hard-to-measure species calculated to be present in neutron irradiated Bioshield wall materials at Shoreham.
The method outlined in NUREG/CR-5849, Appendix Ais used to derive gross activity guideline values for irradiated Bioshield steel and concrete. The gross activity guideline value is defined as:
1 GAG =
f I
I t
2 n
-+-+...G G,
G2 n
where:
2 GAG = gross activity guideline value in dpm/100 cm,
f,
= fraction of total activity represented by nuclide 1, etc and 2
G
= guideline value for the first nuclide, etc in dpm/100 cm.
i To illustrate, the gross activity guideline value calculation for Bioshield steelliner materialis:
The calculated special gross activity guideline values for Bioshield wall concrete and steel are summarized in Table 3 below..
' Attachment 1 GAG =
= 69,000 dprit100cm*.
0.96 0.04 150,000 5,000 Table 3 Summary of Material-Specific Guideline Value Derivation 2
(Assuming GLV = 150,000 dpm/100 cm for H-3, Fe-55)
Material Nuclide Fraction Individual Gross Activity of total")
Nuclide GLV'2' GLV for Material:2>
Concrete H-3 0.64 100,000 80,000 Fe-55 0.34 150,000 Co-60 0.03 5,000 Steel Fe 55 0.96 150,000 69,000 Co-60 0.04 5,000 Table 3 Notes:
(1)
Fraction of total activity in specified material.
2 (2)
Units are dpm/100 cm,
The application of these special gross activity guideli ie values is illustrated by the 50 measurements on Bioshield steel reported in Table 2 and Figure 2. The revised adjustment factor of 25.7 is applied to all measurements above the criticallevel. The results are shown 2
in Table 4. Individual measurement results are well below the 69,000 dpm/100 cm gross activity guideline value. If the data were to be evaluated in accordance with current procedures for evaluating compliance with release criteria, each measurement would be compared to an elevated area guideline value as well (three times.69,000 = 207,000 2
dpm/100 cm ). Such a provision does not seem warranted, based upon the present example.
Assuming the 50 measurements represent a suitable sample of the " population" defined by the concrete portion of the Bioshield C and D ring blocks, the upper limit of the confidence interval about the sample mean is also calculated. As seen in Table 4, the UCL value of 10816 2
dpm/100 cm, is also well below the special gross activity guideline value.
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FIGURE i BIOSHtELD BLOCKS
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Figure 2 Bioshield Wall BIock Measmts - Steel Reported Results vs Criticot Level 1.7 1.6 1.5 1,4
{
l.3 1
1.2 1.1 t
,t 1
8y O.9 l
0,8 gf 0.7 0
0.6 - te m q.
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+
O,5 im/1
) cm' d
O.4 0.3 0.2 O.1 O
y
- 0.1 387 397 407 417 427 Survey Point No.
dpm per 100 cm' wFe Figure 3 a
Bioshield Wall Block Measmts - Concrete Reported Results vs Critical Levet 800 700 LC 'V hw 600 500 400 300 E
d.am/1.
m 8 200 g
100 i_
i
-100
~200
{
-300
-400
-500
-600 388 398 408 423 Survey Point No, 2
dpm per 100 cm wFe.
-*(.,
Table 2 J.
Bloshield Wall Block Measurements - Steel With 1,2 Fe-55 Adjustment Factor
- RWO73F2 type 3 mean 544.8 dpm/100 cm8 Type 3 Okg Fit Cnock count 50 std D 464.3 dpm/100 cm2 FT126 rieg count 1
UCL 655.1 dpm/100 cm2 No. > Lc 16 min
-40.8 dpm/100 cm2 GL vat 5000 dpm/100cm2 No. < Lc 34 max 1591.8 dpm/100 cm8 Range 1633 dpm/100cm8 Avg gepm 103.0 type pointno gepm bepm ett dpm/100 cm8 Lc
+Fe 3
387 116 90 0.049 530.6 574.1 530.6 3
388 109 90 0.049 387.8 564.3 387.8 3
389 148 90 0.049 1183.7 617.1 1420.4 3
390 123 90 0.049 673.5 583.8 808.2 3
391 117 90 0.049 551.0 575.5 551.0 3
392 114 90 0.049 489.8 571.3 489.8 3
393 149 90 0.049 1204.1 618.4 1444.9 3
394 97 90 0 049 142.9 547.0 142.9 3
395 155 90 0.049 1326.5 626.1 1591.8 3
396 96 90 0.049 122.4-545.5 122.4 3
397 145 90 0.049 1122.4 613.2 1346.9 3
398 115 90 0.049 510.2 572.7 510.2 3
399 126 90 0.049 734.7 587.9 881.6 3
400 104 90 0.049 285.7 557.1 285.7 3
401 100 90 0.049 204.1 551.4 204.1 3
402 109 90 0.049 387.8 564.3 387.8 3
403 138 90 0.049 979.6 604.0 1175.5 3
404 105 00 0.049 306.1 558.6 306.1 3
405 110 90 0.049 408.2 565.7 408.2 3
406 109 90 0.049 387.8 564.3 387.8 3
407 129 90 0.049 795.9 591.9 955.1 3
408 103 90 0.049 265.3.
555.7 265.3 3
409 142 90 0.049 1061.2 609.3 1273.5 3
410 92 90 0.049 40.8 539.6 40.8 3
411 148 90 0.049 1181.7 617.1 1420.4 3
412 124 90 0.049 693.3 585.1 832.7 3
413 154 90 0.049 1306.1 624 8 1567.3 3
414 125 90 0.049 714.3 586.5 857.1 3
415 112 90 0.049 449.0 568.5 449.0 3
416 90 90 0.049 0.0 536.7 0.0 3
417 135 90 0.049 918.4 600.0 1102.0 3
418 99 90 0.049 183.7 549.9 183.7 3
419 102 90 0.049 244.9 554.3 244.9 3
420 106 90 0.049 326.5 560.0 326.5 3
421 123 90 0.049 673.5 583.8 808.2 3
422 102 90 0.049 244.9 554.3 244.9 3
423 120 90 0.049 612.2 579.7 734.7 3
424
'94 90 0.049 81.6 542.6 81.6 3
425 109 90 0.049 387.8 564.3 387.8 l
3 426 100 90 C ' 4; 204.1 551.4 204.1 3
427 91 90 0.049 20.4 538.1 20.4 3
428 102 90 0.049 244.9 554.3 244.9 3
429 99 90 0.049 183.7 549.9 183.7 3
430 90 90
' O.049 0.0 536.7 0.0
.j 3
431 88 90 0.049
-40.8 533.7
-40.8 3
'432 97 90 0.049 142.9 547.0 142.9.
l 3
433 112 90 0.049 449.0 568.5 449.0 3
434 111 90 0.049 428.6 567.1 428.6 -
f 3
435 99 90 0.049 183.7 549.9 183.7 3
436 103 90 0.049 265.3 555.7 265.3
'j 8-
o, Table 4 Dioshield Wall Block Measuroments - Steel With 25.7 Fe-55 Adjustment Factor RWO73'F3 mean 7984,8 dpm/100 cm2 Type 3 Bkg Fit Check count 50 std 0 11914.9 dom /100 cm2 FT126 nog count 1
UCL 10815.7 dpm/100 cm2 No. > Lc 16 min
-40.8 dpm/100 cm2 GL va!
69000 dpm/100 cm2 No. < Lc 34 mu 34091.8 dpm/100 cma Range 34133 dpm/100 cm2 Avg gcpm 103 0 typo point _no gcpm bcpm off dom /100 cm2 Lc
+Fe 3
387 116 90 0.049 530.6 5 74.i 530.6 l
3 388 109 90 0.049 387.8 564.3 387.8 3
389 148 90 0.049 1183.7 617.1 30420.4 3
390 123 90 0.049 673.5 583.8 17308.2 3
391 117 90 0.049 551.0 575.5 551.0 3
392 114 90 0 049 489.8 571.3 489.8 3
393 149 90 0.049 1204.1 618.4 30944.9 3
394 97 90 0.049 142.9 547.0 142.9 3
395 155 90 0.049 1326.5 626.1 34091.8 3
396 96 90 0.049 122.4 545.5 122.4 3
397 145 90 0.049 1122.4 613.2 28846.9 3
398 115 90 0.049 510.2 572.7 510.2 3
399 126 90 C.049 734.7 587.9 18881.6 3
400 104 90 0.049 2857 557.1 285.7 3
401 100 90 0.049 204.1 551.4 204.1 3
402 109 90 0 049 387.8 564.3 387.8 3
403 138 90 0.049 979.6 604.0 25175.5 3
404 105 90 0.049 306.1 558.6 306.1 3
405 110 90 0 049 408.2 565.7 403.2 3
406 109 90 0.049 387.8 564.3
.' 8 7. 8 3
407 129 90 0.049 795.9 591.9 20 55.1 3
408 103 90 0.049 265.3 555.7 2 35.3 3
409 142 90 0.049 1061.2 609.3 27273.5 3
410 92 90 0.049 40.8 539.6 40.8 3
411 148 90 0 049 1183.7 617.1 30420.4 3
412 124 90 0.049 693.9 585.1 17832.7 3
413 154 90 0.049 1306.1 624.8 33567.3 3
414 125 90 0.049 714.3 586.5 18357.1 3
415 112 90 0.049 449.0 568.5 449.0 3
416 90 90 0.049 0,0 536.7 0.0 3
417 135 90 0.049 918 4 600.0 23602.0 3
418 99 90 0.049 183.7 549.9 183.7 3
419 102 90 0.049 244.9 554.3 244.9 3
420 106 90 0.049 326.5 560.0 326.5 3
421 123 90 0.049 673.5 583.8 17308.2 3
422 102 90 0.049 244.9 554.3 244.9 3
423 120 90 0.049 612.2 579.7 15734.7 3
424 94 90 0.049 81.6 542.6 81.6 3
425 109 90 0.049 387.8 564.3 387.8 3
426 100 90 0.049 204.1 551.4 204.1 3
427 91 90 0.049 20.4 538.1 20.4 3
428 102 90 0.049 244.9 554.3 244.9 3
429 99 90 0.049 183.7 549.9 183.7 3
430 90 90 0.049 0.0 536.7 0.0 3
431 88 90 0.049
-40.8 533.7
-40.8 3
432 97 90 0.049 142.9 547.0 142.9 3
433 112 90 0.049 449.0 568.5 449.0 3
434 111 90 0.049 428.6 567.1 428.6 3
435 99 90 0.049 183.7 549.9 183.7 3
436 103 90 0.049 265.3 555.7 265.3 9
1
)
Attacnment t Appendix 1
]
April 11, 1994 MEMORAND_U_li To:
Mike Tucker Termination Survey Section Head From:
!!ick Lizzo M-(
Radwaste Engineer _
Subject:
Scaling Factors for Isotopes Present in Blowall Materials The isotopic ration listed below will be used to classify the bioshield wall materials in accordance with 10 CFR 61.56.
Isotope Liner Co-60 concrete Co-60 (Ci/gm)
Normalized (Ci/gm)
Normalized H-3 2.1E-13 0.0279 6.2E-11 23.1581 C-14 2.4E-15 0.0003 1.5E-14 0.0056 Fe -55 1.9E-10 24.7392 3.3E-11 12.2530 Co-6C 7.5E-12 1.0000 2.7E-12 1.0000 Mn-54 7.5E-13 0.0993 NP Ni-59 5.5E-15 0.0007 1.4E-16 0.0001 Ni-63 7.4E-13 0.0982 1.9E-14 0.0070 Nb-94 1.4E-17 0.0000 1.5E-17 0.0000 Tc-99 1.3E-18 0.0000 1.1E-20 0.0000 Sn-119m NP 2.9E-18 0.0000 Sb-125 NP 1.7E-16 0.0001 Te-125m NP 7.4E-24 0.0000 Eu-152 NP 1.4E-12 0.5204 The following information is included for completeness:
Percentage Primary Wall Concrete mass:
1.35E+08 60.7355%
Primary Wall Steel Liner mass:
8.70E+07 gms.
39.2645%
Total Mass concrete & steel:
2.22E&O8 100.0000%
cc:
F.
Petschauer A.
Capristo C.
Adey S.
Moss