NL-08-0634, Request to Implement an Alternative Source Term Response to Request for Additional Information Regarding the Radiological Consequences Analyses

From kanterella
(Redirected from ML081270064)
Jump to navigation Jump to search

Request to Implement an Alternative Source Term Response to Request for Additional Information Regarding the Radiological Consequences Analyses
ML081270064
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 05/05/2008
From: Stinson L
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-08-0634
Download: ML081270064 (30)
v • d • e


Text

L M. Stinson (Mike) Southern Nuclear Vice President Operating Company, Inc.

Fleet Operations Support 40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.5181 A.

Fax 205.992.0341 SOUTHERN COMPANY May 5,2008 Energy to Serve lOur WorlJ SM Docket Nos.: 50-321 NL-08-0634 50-366 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant Request to Implement an Alternative Source Term Response to Request for Additional Information Regarding the Radiological Consequences Analyses Ladies and Gentlemen:

On August 29, 2006 Southern Nuclear Operating Company (SNC) submitted a request to revise the Edwin I. Hatch Nuclear Plant (HNP) licensing/design basis with a full scope implementation of an alternative source term (AST). By letters dated November 6,2006, November 27,2006, January 30,2007, June 22,2007, July 16, 2007, August 13, 2007, October 18, 2007, December 11, 2007, January 24, 2008, February 4, 2008, February 25, 2008, February 27, 2008, March 13, 2008, and April 1, 2008 SNC has submitted further information to support the NRC review of the HNP AST submittal.

By email dated April 7, 2008 and during follow-on teleconferences between SNC and members of the NRC staff on April 15 and 17, 2008 the NRC requested additional information concerning the AST radiological analyses for the four HNP design basis accidents described in Enclosure 1 of the referenced AST submittal.

The enclosures to this letter contain the SNC response to the referenced NRC requests for additional information (RAI).

The 10 CFR 50.92 evaluation and the justification for the categorical exclusion from performing an environmental assessment that were included in the August 29, 2006 submittal continue to remain valid.

(Affirmation and signature are provided on the following page.)

U. S. Nuclear Regulatory Commission NL-08-0634 Page 2 Mr. L. M. Stinson states he is a Vice President of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and to the best of his knowledge and belief, the facts set forth in this letter are true.

This letter contains no NRC commitments. If you have any questions, please advise.

Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY " .1 :

I

~

'f ~

L. M. Stinson Vice President Fleet Operations Support Sworn to and subscribed before me this .1-# day Of_L...tl'Z<......L>4#==r , 2008.

bt2~ I Notary Public My commission expires: ~1 1 0 ...?o /0 LMS/CLT/daj

Enclosures:

1. Response to Request for Additional Information Regarding the Radiological Consequences Analyses
2. Compact Disc (CD) of Updated RADTRAD NIF Files cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. D. R. Madison, Vice President - Hatch Mr. D. H. Jones, Vice President - Engineering RType: CHA02.004 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Acting Regional Administrator Mr. R. E. Martin, NRR Project Manager - Hatch Mr. J. A. Hickey, Senior Resident Inspector - Hatch State of Georgia Mr. N. Holcomb, Commissioner - Department of Natural Resources

Edwin I. Hatch Nuclear Plant Request to Implement an Alternative Source Term Enclosure 1 Response to Request for Additional Information Regarding the Radiological Consequences Analyses

Enclosure 1 Edwin I. Hatch Nuclear Plant Request to Implement an Alternative Source Term Response to Request for Additional Information Regarding the Radiological Consequences Analyses NRC EMAIL QUESTION 1 In Enclosure 1 of your LAR submittal, in Table 6 on page 14, Table 7 (Note) on page 16, and in Appendix A (Conformance Matrix) on page A-1, you state that 10% is added to the core inventory to allow for future fuel changes or power uprates. However, in reviewing the core isotopic activities used in your RADTRAD (NIF) files, I notice that they are equal to the values in Table 7, which you state do not include the 10% increase. Also, the core power used in the runs is simply the current licensed power, plus the 0.5% ECCS flow uncertainty. So, is this 10% increase language a carryover, or typo, from previous analysis intentions, or am I missing something?

SNC RESPONSE In Enclosure 1 of the Alternative Source Term (AST) submittal dated August 29, 2006 Table 6 documented the inputs and assumptions common to multiple Edwin I. Hatch Nuclear Plant (HNP) design basis accident (DBA) AST radiological analyses. As documented in Table 6, SNC chose to incorporate a 10% margin into the core inventory to accommodate potential future fuel changes or power uprates. It is noted that the core inventory, with the 10% margin, is applicable to three of the four HNP DBAs. This 10% margin discussion is not applicable to the main steam line break (MSLB) because no fuel damage is assumed. The applicable MSLB source term is based on the maximum primary coolant iodine activity as allowed by HNP Technical Specifications (reference AST submittal Enclosure 1 section 2.5.5.1) which is independent of power level and core inventory.

AST submittal Enclosure 1 Table 7 documents the referenced core inventory without the 10% margin because, as the table footnote indicates, the core inventory is modified by use of a factor of 1.1 in the LocaDose modeling for the three affected HNP DBAs. However, Enclosure 1 Table 7 has been updated, and is provided below, so each listed isotope reflects the 10% margin.

NL-08-0634 E1-1

Enclosure 1 Edwin I. Hatch Nuclear Plant Request to Implement an Alternative Source Term Response to Request for Additional Information Regarding the Radiological Consequences Analyses_______________________

Table 7. Core Inventory Source Source Source Source Grp Isotope (Ci/MWt) Grp Isotope (Ci/MWt) Grp Isotope (Ci/MWt) Grp Isotope (Ci/MWt)

I-129 1.35E-03 Se-79 1.83E-02 Ru-103 4.68E+04 Sm-151 2.09E+01 I-130 1.16E+03 Sb-124 4.99E+01 Ru-105 3.27E+04 Sm-153 1.51E+04 8 - Noble Metals I-131 2.99E+04 Sb-125 6.71E+02 Ru-106 1.87E+04 Eu-152 5.17E-01 1, 2, 3 - Iodines I-132 4.32E+04 Sb-126 3.94E+01 Rh103m 4.21E+04 Eu-154 4.32E+02 I-133 6.07E+04 Sb126m 1.50E+01 Rh-105 2.99E+04 Eu-155 3.03E+02 I-134 6.66E+04 Sb-127 3.28E+03 Rh-106 2.00E+04 Eu-156 5.60E+03 9 - Lanthanides I-135 5.68E+04 Sb-129 9.74E+03 Pd-107 4.52E-03 Am-241 7.55E+00 6 - Tellurium Group I-136 2.69E+04 Te125m 1.46E+02 Pd-109 1.03E+04 Am-242 3.14E+03 I-137 2.62E+04 Te-127 3.30E+03 Y-89m 6.90E-04 Am242m 1.02E+00 I-138 1.30E+04 Te127m 4.40E+02 Y--90 3.52E+03 Am-243 8.21E-01 Kr-83m 3.63E+03 Te-129 9.58E+03 Y-90m 5.07E-01 Cm-242 1.85E+03 Kr-85 4.16E+02 Te129m 1.42E+03 Y--91 3.55E+04 Cm-243 9.89E-01 Kr-85m 7.61E+03 Te-131 2.65E+04 Y-91m 2.01E+04 Cm-244 1.16E+02 Kr-87 1.45E+04 Te131m 4.33E+03 Y--92 3.79E+04 Cm-245 1.10E-02 Kr-88 2.05E+04 Te-132 4.24E+04 Y--93 4.40E+04 Cm-246 1.82E-03 4 - Noble Gases Kr-89 2.49E+04 Te-133 3.56E+04 Y--94 4.46E+04 Br-82 1.99E+02 11 - Halogens Xe131m 3.33E+02 Te133m 2.19E+04 Y--95 4.80E+04 Br-83 3.63E+03 Xe-133 5.80E+04 Te-134 4.98E+04 Zr-93 1.05E-01 Br-84 6.26E+03 Xe133m 1.74E+03 Sr-89 2.74E+04 Zr-95 5.25E+04 Br-85 7.51E+03 Xe-135 2.08E+04 Sr-90 3.31E+03 Zr-97 5.49E+04 Br-87 1.22E+04 Xe135m 1.20E+04 Sr-91 3.47E+04 Nb-93m 9.03E-03 Br-88 1.31E+04 9 - Lanthanides 7 - Strontium, Barium Xe-137 5.29E+04 Sr-92 3.76E+04 Nb-95 5.27E+04 Ce-141 4.93E+04 Xe-138 4.97E+04 Sr-93 4.29E+04 Nb-95m 3.71E+02 Ce-143 4.54E+04 Rb-86 7.77E+01 Sr-94 4.06E+04 Nb-97 5.54E+04 Ce-144 4.06E+04 Rb-88 2.08E+04 Sr-95 3.77E+04 La-140 5.37E+04 Np-237 1.77E-02 Rb-89 2.66E+04 Ba136m 3.96E+02 La-141 4.92E+04 Np-238 1.63E+04 12 - Cerium Group Rb-90 2.57E+04 Ba137m 4.31E+03 La-142 4.74E+04 Np-239 6.28E+05 5 - Alkali Metals Cs-134 7.51E+03 Ba-139 5.40E+04 La-143 4.52E+04 Pu-236 3.01E-02 Cs134m 1.82E+03 Ba-140 5.20E+04 Pr-143 4.45E+04 Pu-237 1.14E-01 Cs-135 2.59E-02 Ba-141 4.90E+04 Pr-144 4.09E+04 Pu-238 1.44E+02 Cs-136 2.40E+03 Co-58 1.63E+02 Pr144m 4.88E+02 Pu-239 1.42E+01 8 - Noble Metals Cs-137 4.55E+03 Co-60 4.70E+02 Nd-147 1.98E+04 Pu-240 1.96E+01 Cs-138 5.52E+04 Mo-99 5.66E+04 Pm-147 4.98E+03 Pu-241 5.75E+03 Cs-139 5.23E+04 Tc-99 5.77E-01 Pm-148 8.60E+03 Pu-242 6.81E-02 Tc-99m 4.98E+04 Pm148m 1.28E+03 Pu-243 1.17E+04 Tc-101 5.09E+04 Pm-149 1.76E+04 Pm-151 6.04E+03 Note: The inventory shown in the table includes a margin of 10% for future fuel changes or power uprates.

In calculating doses, the progeny of these isotopes are also included.

NL-08-0634 E1-2 Edwin I. Hatch Nuclear Plant Request to Implement an Alternative Source Term Response to Request for Additional Information Regarding the Radiological Consequences Analyses_______________________

For the three affected HNP DBAs, specifically the loss-of-coolant accident (LOCA), control rod drop accident (CRDA), and fuel handling accident (FHA),

the 10% margin is incorporated in both the offsite dose results and main control room (MCR) dose results presented in AST submittal Enclosure 1. The LOCA MCR dose results presented in AST submittal Enclosure 1 Table 20 establish the limiting HNP MCR unfiltered inleakage of 115 cubic feet per minute (cfm).

The core inventory in the updated Table 7 (with the 10% margin) was used in LocaDose to calculate the doses due to airborne activity inside the MCR, the external shine dose from the turbine building (TB) air (more specifically the shine dose due to airborne activity inside the TB), and the ingress/egress dose while traversing through the TB. Hence, these three components of the MCR dose, as shown in AST submittal Enclosure 1 Table 20, include the 10% margin. The only other component of the MCR dose, as shown in Table 20, is other external shine sources, with a dose of 0.03 rem TEDE. The MCR dose due to other external shine sources was calculated using the original NUREG-0737 source term which reflects a core inventory with greater than 10% margin to the original AST submittal Enclosure 1 Table 7. For example, the I-131 release from the core was approximately 3.2E7 Ci for the NUREG-0737 review versus 2.3E7 Ci for AST.

The total noble gas releases were 8.6E8 Ci for the NUREG-0737 review versus 3.3E8 Ci for AST. Therefore, the LOCA MCR dose results presented in the referenced Table 20 are bounding with a margin of 10% included.

The RADTRAD input files referenced were submitted in the SNC letter dated November 27, 2006. As noted in that letter, these input files were provided to facilitate the NRC staff review of the HNP AST submittal by supporting the performance of confirmatory calculations using the RADTRAD code by the NRC staff. The HNP AST design basis calculations use the LocaDose code as documented in the HNP AST submittal. Therefore any RADTRAD results, while useful for NRC confirmatory calculations, do not represent the submitted HNP AST licensing basis. Consistent with the updating of AST submittal Enclosure 1 Table 7 to explicitly include the 10% margin, updated RADTRAD NIF input files which reflect the 10% margin are provided on compact disc as Enclosure 2. In addition, subsequent to the previous submittal of the RADTRAD input files in 2006, it was identified that some of the isotope group assignments should be changed but evaluation indicated that the overall conclusions were not changed.

Therefore, given the need to update the RADTRAD NIF files, the necessary isotope group assignments were changed as well. Of the RADTRAD input files supplied previously, only the RADTRAD NIF files needed to be changed to explicitly include the 10% margin.

The results of three RADTRAD cases (files) need to be added to determine the bounding LOCA MCR dose. Those RADTRAD file names are as follows:

  • HatchLOCA4CR-ContainmentLeakageFinal.psf
  • HatchLOCA4CR-ESFLeakageFinal.psf
  • HatchLOCA4CR-PlantVentFinal.psf NL-08-0634 E1-3 Edwin I. Hatch Nuclear Plant Request to Implement an Alternative Source Term Response to Request for Additional Information Regarding the Radiological Consequences Analyses_______________________

NRC EMAIL QUESTION 2 Also, I would just like to know the enrichment and burnup used in the ORIGEN runs. I could not locate it in the LAR.

SNC RESPONSE As documented in AST submittal Enclosure 1 Table 6, the equilibrium core inventory of fission products per unit power (Ci/MWt) was generated using the ORIGEN2 computer program based on a 24-month fuel cycle. A comparison of the fission product inventory of a single-batch core versus the fission product inventory of a multi-batch core demonstrates that, for DBA radiologically significant isotopes, isotope production due to uniform irradiation at constant power is a good approximation to isotope production from a multi-batch core under the same average power. The equilibrium core is assumed to be composed of a single uniform batch of GE14 fuel at 4.1% enrichment, with an end of cycle core average exposure of approximately 36,600 MWd/MT, or approximately 1330 EFPD.

It is noted that the resultant core inventory by isotope (with the margin of 10% as documented in the updated Table 7 provided in the response to NRC Email Question 1) is the actual input to the HNP AST analyses. Consequently, fuel designs reflecting different enrichments and burnups can be used as long as the resultant core inventory is bounded by the core inventory provided in the updated Table 7.

NL-08-0634 E1-4

Edwin I. Hatch Nuclear Plant Request to Implement an Alternative Source Term Enclosure 2 Compact Disc (CD) of Updated RADTRAD NIF Files

Nuclide Inventory Name:

ST general Power Level:

0.1000E+01 Nuclides:

63 Nuclide 001:

Kr-83m 1

0.6696E+04 0.8300E+02 3.63E+03 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 002:

Kr-85m 1

0.1612800000E+05 0.8500E+02 7.61E+03 Kr-85 0.2100E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 003:

Kr-85 1

0.338613048E+09 0.8500E+02 4.16E+02 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 004:

Kr-87 1

0.4578000000E+04 0.8700E+02 1.45E+04 Rb-87 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 005:

Kr-88 1

0.1022400000E+05 0.8800E+02 2.05E+04 Rb-88 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 006:

Rb-86 3

0.1612224000E+07 0.8600E+02 7.77E+01

none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 007:

Rb-88 3

0.1062000000E+04 0.8800E+02 2.08E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 008:

Sr-89 5

0.4363200000E+07 0.8900E+02 2.74E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 009:

Sr-90 5

0.9189573120E+09 0.9000E+02 3.31E+03 Y-90 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 010:

Sr-91 5

0.3420000000E+05 0.9100E+02 3.47E+04 Y-91m 0.5800E+00 Y-91 0.4200E+00 none 0.0000E+00 Nuclide 011:

Sr-92 5

0.9756000000E+04 0.9200E+02 3.76E+04 Y-92 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 012:

Y-90 9

0.2304000000E+06 0.9000E+02 3.52E+03 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00

Nuclide 013:

Y-91 9

0.5055264000E+07 0.9100E+02 3.55E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 014:

Y-92 9

0.1274400000E+05 0.9200E+02 3.78E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 015:

Y-93 9

0.3636000000E+05 0.9300E+02 4.40E+04 Zr-93 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 016:

Zr-95 9

0.5527872000E+07 0.9500E+02 5.25E+04 Nb-95m 0.7000E-02 Nb-95 0.9900E+00 none 0.0000E+00 Nuclide 017:

Zr-97 9

0.6084000000E+05 0.9700E+02 5.50E+04 Nb-97m 0.9500E+00 Nb-97 0.5300E-01 none 0.0000E+00 Nuclide 018:

Nb-95 9

0.3036960000E+07 0.9500E+02 5.27E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 019:

Mo-99 7

0.2376000000E+06 0.9900E+02 5.67E+04 Tc-99m 0.8800E+00 Tc-99 0.1200E+00 none 0.0000E+00 Nuclide 020:

Tc-99m 7

0.2167200000E+05 0.9900E+02 4.98E+04 Tc-99 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 021:

Ru-103 7

0.3393792000E+07 0.1030E+03 4.68E+04 Rh-103m 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 022:

Ru-105 7

0.1598400000E+05 0.1050E+03 3.27E+04 Rh-105 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 023:

Ru-106 7

0.3181248000E+08 0.1060E+03 1.87E+04 Rh-106 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 024:

Rh-105 7

0.1272960000E+06 0.1050E+03 2.99E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 025:

Sb-127 4

0.3326400000E+06 0.1270E+03 3.28E+03

Te-127m 0.1800E+00 Te-127 0.8200E+00 none 0.0000E+00 Nuclide 026:

Sb-129 4

0.1555200000E+05 0.1290E+03 9.74E+03 Te-129m 0.2200E+00 Te-129 0.7700E+00 none 0.0000E+00 Nuclide 027:

Te-127 4

0.3366000000E+05 0.1270E+03 3.30E+03 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 028:

Te-127m 4

0.9417600000E+07 0.1270E+03 4.40E+02 Te-127 0.9800E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 029:

Te-129 4

0.4176000000E+04 0.1290E+03 9.58E+03 I-129 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 030:

Te-129m 4

0.2903040000E+07 0.1290E+03 1.42E+03 Te-129 0.6500E+00 I-129 0.3500E+00 none 0.0000E+00 Nuclide 031:

Te-131m 4

0.1080000000E+06 0.1310E+03 4.33E+03 Te-131 0.2200E+00 I-131 0.7800E+00 none 0.0000E+00

Nuclide 032:

Te-132 4

0.2815200000E+06 0.1320E+03 4.24E+04 I-132 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 033:

I-131 2

0.6946560000E+06 0.1310E+03 2.99E+04 Xe-131m 0.1100E-01 none 0.0000E+00 none 0.0000E+00 Nuclide 034:

I-132 2

0.8280000000E+04 0.1320E+03 4.32E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 035:

I-133 2

0.7488000000E+05 0.1330E+03 6.07E+04 Xe-133m 0.2900E-01 Xe-133 0.9700E+00 none 0.0000E+00 Nuclide 036:

I-134 2

0.3156000000E+04 0.1340E+03 6.66E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 037:

I-135 2

0.2379600000E+05 0.1350E+03 5.68E+04 Xe-135m 0.1500E+00 Xe-135 0.8500E+00 none 0.0000E+00 Nuclide 038:

Xe-133 1

0.4531680000E+06 0.1330E+03 5.80E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 039:

Xe-133m 1

0.1926720000E+06 0.1330E+03 1.74E+03 Xe-133 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 040:

Xe-135 1

0.3272400000E+05 0.1350E+03 2.08E+04 Cs-135 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 041:

Xe-135m 1

0.91800000E+03 0.1350E+03 1.20E+04 Xe-135 0.9940E+00 Cs-135 0.6000E-03 none 0.0000E+00 Nuclide 042:

Xe-138 1

0.85200000E+03 0.1380E+03 4.97E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 043:

Cs-134 3

0.6507177120E+08 0.1340E+03 7.51E+03 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 044:

Cs-136 3

0.1131840000E+07 0.1360E+03 2.40E+03

none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 045:

Cs-137 3

0.9467280000E+09 0.1370E+03 4.55E+03 Ba-137m 0.9500E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 046:

Ba-139 6

0.4962000000E+04 0.1390E+03 5.40E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 047:

Ba-140 6

0.1100736000E+07 0.1400E+03 5.20E+04 La-140 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 048:

La-140 9

0.1449792000E+06 0.1400E+03 5.37E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 049:

La-141 9

0.1414800000E+05 0.1410E+03 4.92E+04 Ce-141 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 050:

La-142 9

0.5550000000E+04 0.1420E+03 4.74E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00

Nuclide 051:

Ce-141 8

0.2808086400E+07 0.1410E+03 4.93E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 052:

Ce-143 8

0.1188000000E+06 0.1430E+03 4.54E+04 Pr-143 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 053:

Ce-144 8

0.2456352000E+08 0.1440E+03 4.06E+04 Pr-144m 0.1800E-01 Pr-144 0.9800E+00 none 0.0000E+00 Nuclide 054:

Pr-143 9

0.1171584000E+07 0.1430E+03 4.44E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 055:

Nd-147 9

0.9486720000E+06 0.1470E+03 1.98E+04 Pm-147 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 056:

Np-239 8

0.2034720000E+06 0.2390E+03 6.28E+05 Pu-239 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 057:

Pu-238 8

0.2768863824E+10 0.2380E+03 1.44E+02 U-234 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 058:

Pu-239 8

0.7594336440E+12 0.2390E+03 1.42E+01 U-235 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 059:

Pu-240 8

0.2063867E+11 0.240E+03 1.96E+01 U-236 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 060:

Pu-241 8

0.473364E+09 0.241E+03 5.75E+03 Am-241 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 061:

Am-241 9

0.13664441E+11 0.241E+03 7.55E+00 Np-237 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 062:

Cm-242 9

0.14083200E+08 0.242E+03 1.85E+03 Pu-238 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 063:

Cm-244 9

0.56488104E+09 0.244E+03 1.16E+02

Pu-240 0.1000E+01 none 0.0000E+00 none 0.0000E+00 End of Nuclear Inventory File

Nuclide Inventory Name:

ST for FHA (enhanced Kr-85 and I-131)

Power Level:

0.1000E+01 Nuclides:

63 Nuclide 001:

Kr-83m 1

0.6696E+04 0.8300E+02 3.63E+03 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 002:

Kr-85m 1

0.1612800000E+05 0.8500E+02 7.61E+03 Kr-85 0.2100E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 003:

Kr-85 1

0.338613048E+09 0.8500E+02 8.32E+02 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 004:

Kr-87 1

0.4578000000E+04 0.8700E+02 1.45E+04 Rb-87 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 005:

Kr-88 1

0.1022400000E+05 0.8800E+02 2.05E+04 Rb-88 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 006:

Rb-86 3

0.1612224000E+07 0.8600E+02 7.77E+01

none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 007:

Rb-88 3

0.1062000000E+04 0.8800E+02 2.08E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 008:

Sr-89 5

0.4363200000E+07 0.8900E+02 2.74E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 009:

Sr-90 5

0.9189573120E+09 0.9000E+02 3.31E+03 Y-90 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 010:

Sr-91 5

0.3420000000E+05 0.9100E+02 3.47E+04 Y-91m 0.5800E+00 Y-91 0.4200E+00 none 0.0000E+00 Nuclide 011:

Sr-92 5

0.9756000000E+04 0.9200E+02 3.76E+04 Y-92 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 012:

Y-90 9

0.2304000000E+06 0.9000E+02 3.52E+03 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00

Nuclide 013:

Y-91 9

0.5055264000E+07 0.9100E+02 3.55E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 014:

Y-92 9

0.1274400000E+05 0.9200E+02 3.78E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 015:

Y-93 9

0.3636000000E+05 0.9300E+02 4.40E+04 Zr-93 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 016:

Zr-95 9

0.5527872000E+07 0.9500E+02 5.25E+04 Nb-95m 0.7000E-02 Nb-95 0.9900E+00 none 0.0000E+00 Nuclide 017:

Zr-97 9

0.6084000000E+05 0.9700E+02 5.50E+04 Nb-97m 0.9500E+00 Nb-97 0.5300E-01 none 0.0000E+00 Nuclide 018:

Nb-95 9

0.3036960000E+07 0.9500E+02 5.27E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 019:

Mo-99 7

0.2376000000E+06 0.9900E+02 5.67E+04 Tc-99m 0.8800E+00 Tc-99 0.1200E+00 none 0.0000E+00 Nuclide 020:

Tc-99m 7

0.2167200000E+05 0.9900E+02 4.98E+04 Tc-99 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 021:

Ru-103 7

0.3393792000E+07 0.1030E+03 4.68E+04 Rh-103m 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 022:

Ru-105 7

0.1598400000E+05 0.1050E+03 3.27E+04 Rh-105 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 023:

Ru-106 7

0.3181248000E+08 0.1060E+03 1.87E+04 Rh-106 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 024:

Rh-105 7

0.1272960000E+06 0.1050E+03 2.99E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 025:

Sb-127 4

0.3326400000E+06 0.1270E+03 3.28E+03

Te-127m 0.1800E+00 Te-127 0.8200E+00 none 0.0000E+00 Nuclide 026:

Sb-129 4

0.1555200000E+05 0.1290E+03 9.74E+03 Te-129m 0.2200E+00 Te-129 0.7700E+00 none 0.0000E+00 Nuclide 027:

Te-127 4

0.3366000000E+05 0.1270E+03 3.30E+03 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 028:

Te-127m 4

0.9417600000E+07 0.1270E+03 4.40E+02 Te-127 0.9800E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 029:

Te-129 4

0.4176000000E+04 0.1290E+03 9.58E+03 I-129 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 030:

Te-129m 4

0.2903040000E+07 0.1290E+03 1.42E+03 Te-129 0.6500E+00 I-129 0.3500E+00 none 0.0000E+00 Nuclide 031:

Te-131m 4

0.1080000000E+06 0.1310E+03 4.33E+03 Te-131 0.2200E+00 I-131 0.7800E+00 none 0.0000E+00

Nuclide 032:

Te-132 4

0.2815200000E+06 0.1320E+03 4.24E+04 I-132 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 033:

I-131 2

0.6946560000E+06 0.1310E+03 4.78E+04 Xe-131m 0.1100E-01 none 0.0000E+00 none 0.0000E+00 Nuclide 034:

I-132 2

0.8280000000E+04 0.1320E+03 4.32E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 035:

I-133 2

0.7488000000E+05 0.1330E+03 6.07E+04 Xe-133m 0.2900E-01 Xe-133 0.9700E+00 none 0.0000E+00 Nuclide 036:

I-134 2

0.3156000000E+04 0.1340E+03 6.66E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 037:

I-135 2

0.2379600000E+05 0.1350E+03 5.68E+04 Xe-135m 0.1500E+00 Xe-135 0.8500E+00 none 0.0000E+00 Nuclide 038:

Xe-133 1

0.4531680000E+06 0.1330E+03 5.80E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 039:

Xe-133m 1

0.1926720000E+06 0.1330E+03 1.74E+03 Xe-133 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 040:

Xe-135 1

0.3272400000E+05 0.1350E+03 2.08E+04 Cs-135 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 041:

Xe-135m 1

0.91800000E+03 0.1350E+03 1.20E+04 Xe-135 0.9940E+00 Cs-135 0.6000E-03 none 0.0000E+00 Nuclide 042:

Xe-138 1

0.85200000E+03 0.1380E+03 4.97E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 043:

Cs-134 3

0.6507177120E+08 0.1340E+03 7.51E+03 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 044:

Cs-136 3

0.1131840000E+07 0.1360E+03 2.40E+03

none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 045:

Cs-137 3

0.9467280000E+09 0.1370E+03 4.55E+03 Ba-137m 0.9500E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 046:

Ba-139 6

0.4962000000E+04 0.1390E+03 5.40E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 047:

Ba-140 6

0.1100736000E+07 0.1400E+03 5.20E+04 La-140 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 048:

La-140 9

0.1449792000E+06 0.1400E+03 5.37E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 049:

La-141 9

0.1414800000E+05 0.1410E+03 4.92E+04 Ce-141 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 050:

La-142 9

0.5550000000E+04 0.1420E+03 4.74E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00

Nuclide 051:

Ce-141 8

0.2808086400E+07 0.1410E+03 4.93E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 052:

Ce-143 8

0.1188000000E+06 0.1430E+03 4.54E+04 Pr-143 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 053:

Ce-144 8

0.2456352000E+08 0.1440E+03 4.06E+04 Pr-144m 0.1800E-01 Pr-144 0.9800E+00 none 0.0000E+00 Nuclide 054:

Pr-143 9

0.1171584000E+07 0.1430E+03 4.44E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 055:

Nd-147 9

0.9486720000E+06 0.1470E+03 1.98E+04 Pm-147 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 056:

Np-239 8

0.2034720000E+06 0.2390E+03 6.28E+05 Pu-239 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 057:

Pu-238 8

0.2768863824E+10 0.2380E+03 1.44E+02 U-234 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 058:

Pu-239 8

0.7594336440E+12 0.2390E+03 1.42E+01 U-235 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 059:

Pu-240 8

0.2063867E+11 0.240E+03 1.96E+01 U-236 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 060:

Pu-241 8

0.473364E+09 0.241E+03 5.75E+03 Am-241 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 061:

Am-241 9

0.13664441E+11 0.241E+03 7.55E+00 Np-237 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 062:

Cm-242 9

0.14083200E+08 0.242E+03 1.85E+03 Pu-238 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 063:

Cm-244 9

0.56488104E+09 0.244E+03 1.16E+02

Pu-240 0.1000E+01 none 0.0000E+00 none 0.0000E+00 End of Nuclear Inventory File

Retrieved from "https://kanterella.com/w/index.php?title=NL-08-0634,_Request_to_Implement_an_Alternative_Source_Term_Response_to_Request_for_Additional_Information_Regarding_the_Radiological_Consequences_Analyses&oldid=2569789"