ML14029A066

From kanterella
Jump to navigation Jump to search
Calculation RA-0050, Revision 0 - Kewaunee Resin Cask Drop Dose Consequence Analysis
ML14029A066
Person / Time
Site: Kewaunee Dominion icon.png
Issue date: 01/16/2014
From:
Dominion Energy Kewaunee
To:
Office of Nuclear Reactor Regulation
References
13-495A RA-0050, Rev 0
Download: ML14029A066 (13)
v • d • e


Text

CALCULATION RA-0050, REVISION 0 KEWAUNEE RESIN CASK DROP DOSE CONSEQUENCE ANALYSIS

Calculation Worksheet Dominion- I.aluato RA S-005Re . Pa .e2 0 Sf1 Instructions: To update the Table of Contents page numbers, click within the Table of Contents to select the table, then select "Print Preview," (Click the Office Button at the upper left of the computer screen; then select "Print," and then "Print Preview") close "Print Preview." The page numbers should update.

Table of Contents

1. RECORD OF REVISION AND ADDENDA ........................................................................................................................... 3
2. CUMULATIVE EFFECTS REVIEW (REQUIRED FOR REVISIONS AND ADDENDA) ................................... 3
3. REFERENCES ............................................................................................................................................................................... 3
4. COM PUTER CODES USED ...................................................................................................................................................... 3
5. Identification of Com puter Inputs and Outputs ....................................................................................... 3
6. Purpose ........................................................................................................................................................... 3
7. Background (OPTIONAL) ............................................................................................................................... 4
8. Design Inputs .................................................................................................................................................... 4
9. Assum ptions ..................................................................................................................................................... 6
10. Methodology ..................................................................................................................................................... 7
11. Calculations ...................................................................................................................................................... 7
12. Acceptance Criteria (OPTIONAL) ............................................................................................................ 9
13. Results and/or Conclusions ............................................................................................................................ 10
14. Precautions and Limitations ........................................................................................................................... 10
15. Recom mendations (OPTIONAL) .................................................................................................................... 10
16. Calculation Review Checklist ......................................................................................................................... 10
17. List of Attachments ......................................................................................................................................... 10 729292 (Mar 2012)

Calculation Worksheet SDominion- I.aclto RA g-005 Rev 0 Pae3of1

1. Record of Revision and Addenda Original Issue
2. Cumulative Effects Review (Required for Revisions and Addenda)

N/A

3. References
1) NRC Regulatory Guide 1.183 Rev. 0, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors," July 2000.
2) Waste Manifest and Supporting Documentation for Kewaunee Resin Shipment SPF-0513-01 (Selected pages included as Attachment 2 of this calculation).
3) EPA 400-R-92-001, "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents," May 1992.
4) Calculation CN-CRA-00-2, Revision 3, "Kewaunee - LOCA Doses with Increased Control Room Unfiltered Inleakage," 5/10/07.
5) EPA 402-R-93-081 (Federal Guidance Report No. 12), "External Exposure to Radionuclides In Air, Water, and Soil," September 1993.
6) EPA 520/1-88-020 (Federal Guidance Report No. 11), "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," September 1988.
4. Computer Codes Used None
5. Identification of Computer Inputs and Outputs None
6. Purpose The purpose of this calculation is to determine the dose consequences at the Kewaunee site boundary resulting from a resin cask drop accident.

729292 (Mar 2012)

Mbk Calculation Worksheet W"Dominion- ltinR I -0~~s 5.ev -.

Cac ag f1 0

7. Background (OPTIONAL)

N/A

&. Design Inputs Inhalation rate = 3.5E-4 m3/sec (Reference 1)

X/Q = 2.23E-4 sec/m 3 (95 th Percentile Worst Case X/Q, Reference 4)

Bounding Resin Cask Nuclide Content (Reference 2):

Nuclide mCi H-3 1.77E+01 C-14 4.26E+01 Mn-54 7.80E+02 Fe-55 5.28E+03 Co-57 4.05E+02 Co-58 5.64E+03 Co-60 6.88E+03 Ni-59 5.64E+02 Ni-63 6.85E+04 Zn-65 7.08E+01 Sr-89 5.44E-01 Sr-90 3.24E+00 Sb-1 25 3.61 E+02 Cs-137 1.85E+02 Pu-238 1.63E-02 Pu-239 1.10E-02 Pu-241 4.18E+00 Am-241 5.35E-03 Cm-243 5.38E-03 Ce-144 5.58E+01 0.946 is the fraction of the Cs-137 nuclear transformations forming Ba-137m. (Reference 5 pg. 203) 729292 (Mar 2012)

Calculation Worksheet r Dominion I aluato RA~-05Re. S 0Pae5 Sf1 Effective Dose Coefficients for Air Submersion (Reference 5, Table 111.1):

Dose Coefficient Nuclide Sv m3/Bq s H-3 3.13E-19 C-14 2.24E-19 Mn-54 4.09E-14 Fe-55 O.OOE+00 Co-57 5.61E-15 Co-58 4.76E-14 Co-60 1.26E-13 Ni-59 O.OOE+00 Ni-63 O.OOE+00 Zn-65 2.90E-14 Sr-89 7.73E-17 Sr-90 7.53E-18 Sb-125 2.02E-14 Cs-137 7.74E-18 Pu-238 4.88E-18 Pu-239 4.24E-18 Pu-241 7.25E-20 Am-241 8.18E-16 Cm-243 5.88E-15 Ce-144 8.53E-16 Ba-137m 2.88E-14 729292 (Mar 2012)

hCalculation Worksheet

'Dominion- C l R0 R 0 ..* 6 of 1 0 Effective Committed Dose Equivalent per Unit Intake (Reference 6, Table 2.1):

Inhalation Nuclide Sv / Bq H-3 1.73E-11 C-14 5.64E-10 Mn-54 1.81E-09 Fe-55 7.26E-10 Co-57 2.45E-09 Co-58 2.94E-09 Co-60 5.91E-08 Ni-59 3.58E-10 Ni-63 8.39E-10 Zn-65 5.51E-09 Sr-89 1.12E-08 Sr-90 3.51E-07 Sb-125 3.30E-09 Cs-137 8.63E-09 Pu-238 1.06E-04 Pu-239 1.16E-04 Pu-241 2.23E-06 Am-241 1.20E-04 Cm-243 8.30E-05 Ce-144 1.01E-07 Ba-137m 0.00E+00

9. Assumptions
1. Assume the resin release fraction to be either 10% or 100%. 10% should be conservative, while 100%

produces a limiting case.

2. Accident time interval = 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (Assumption. Given that atmospheric dispersion is modeled as instantaneous and no decay over the release time is modeled, the cumulative dose is independent of the release interval provided that the dose is integrated over the entire release interval.)
3. No decay from the date of plant shutdown is modeled. This is a conservative assumption 729292 (Mar 2012)

Calculation Worksheet Cacuaton R -0 mw-Dominion- 5 Re. 0 Pa e7 6f1

10. Methodology The integrated dose over a given time period is equal to the sum of the external dose (EDE) and the internal dose (CEDE). The EDE for a given nuclide is calculated as the product of the curies released, the X/Q, and the effective dose coefficient for air submersion. The CEDE for a given nuclide is calculated as the product of the curies released, the X/Q, the inhalation rate, and the committed dose equivalent per Unit Intake coefficient.

Two cases will be evaluated, corresponding to the 10% and 100% release fractions.

11. Calculations An example calculation of the EDE dose from H-3 is as follows.

EDE = (1.77E-2 Ci)(2.23E-4 sec/m3)(3.13E-19 Sv m3/Bq sec)(3.7E10 Bq/Ci)(100 Rem/Sv) = 4.58E-12 Rem An example calculation of the CEDE dose from H-3 is as follows.

CEDE = (1.77E-2 Ci)(2.23E-4 sec/m 3)(3.5E-4 m3/sec)(1.73E-11 Sv/Bq)(3.7E10 Bq/Ci)(100 Rem/Sv) = 8.84E-8 Rem 729292 (Mar 2012)

Calculation Worksheet mr-Dominion- I Calulaio RA05 Rev-. 0 ae8 f1 The 100% release fraction case is as follows, for a total dose of 0.148 Rem:

Table 1: Dose Consequences from a Resin Cask Drop Accident with a 100% Release Fraction EDE CEDE Curies External 1 Hr Inhalation Total Dose Nuclide Released Dose (Rem) Dose (Rem) (Rem)

H-3 1.77E-02 4.57E-12 8.84E-08 8.84E-08 C-14 4.26E-02 7.87E-12 6.94E-06 6.94E-06 Mn-54 7.80E-01 2.63E-05 4.08E-04 4.34E-04 Fe-55 5.28E+00 0.OOE+00 1.11E-03 1.11E-03 Co-57 4.05E-01 1.87E-06 2.87E-04 2.88E-04 Co58 5.64E+00 2.22E-04 4.79E-03 5.01E-03 Co-60 6.88E+00 7.15E-04 1.17E-01 1.18E-01 Ni-59 5.64E-01 0.OOE+00 5.83E-05 5.83E-05 Ni-63 6.85E+01 0.OOE+00 1.66E-02 1.66E-02 Zn-65 7.08E-02 1.69E-06 1.13E-04 1.14E-04 Sr-89 5.44E-04 3.47E-11 1.76E-06 1.76E-06 Sr-90 3.24E-03 2.01E-11 3.28E-04 3.28E-04 Sb-125 3.61E-01 6.02E-06 3.44E-04 3.50E-04 Cs-137 1.85E-01 1.18E-09 4.61E-04 4.61E-04 Pu-238 1.63E-05 6.56E-14 4.99E-04 4.99E-04 Pu-239 1.10E-05 3.85E-14 3.68E-04 3.68E-04 Pu-241 4.18E-03 2.50E-13 2.69E-03 2.69E-03 Am-241 5.35E-06 3.61E-12 1.85E-04 1.85E-04 Cm-243 5.38E-06 2.61E-11 1.29E-04 1.29E-04 Ce-144 5.58E-02 3.93E-08 1.63E-03 1.63E-03 Ba-137m 1.75E-01 4.16E-06 O.OOE+00 4.16E-06 Total 9.77E-04 1.47E-01 1.48E-01 729292 (Mar 2012)

Calculation Worksheet wrD *_minion- Calculatio RA 0 5 Rev.* 0 a e9 Sf1 The 10% release fraction case is as follows, for a total dose of 0.015 Rem:

Table 2: Dose Consequences from a Resin Cask Drop Accident with a 10% Release Fraction EDE CEDE Curies External 1 Hr Inhalation Total Dose Nuclide Released Dose (Rem) Dose (Rem) (Rem)

H-3 1.77E-03 4.57E-13 8.84E-09 8.84E-09 C-14 4.26E-03 7.87E-13 6.94E-07 6.94E-07 Mn-54 7.80E-02 2.63E-06 4.08E-05 4.34E-05 Fe-55 5.28E-01 0.OOE+00 1.11E-04 1.11E-04 Co-57 4.05E-02 1.87E-07 2.87E-05 2.88E-05 Co58 5.64E-01 2.22E-05 4.79E-04 5.01E-04 Co-60 6.88E-01 7.15E-05 1.17E-02 1.18E-02 Ni-59 5.64E-02 O.OOE+00 5.83E-06 5.83E-06 Ni-63 6.85E+00 0.OOE+00 1.66E-03 1.66E-03 Zn-65 7.08E-03 1.69E-07 1.13E-05 1.14E-05 Sr-89 5.44E-05 3.47E-12 1.76E-07 1.76E-07 Sr-90 3.24E-04 2.01E-12 3.28E-05 3.28E-05 Sb-125 3.61E-02 6.02E-07 3.44E-05 3.50E-05 Cs-137 1.85E-02 1.18E-10 4.61E-05 4.61E-05 Pu-238 1.63E-06 6.56E-15 4.99E-05 4.99E-05 Pu-239 1.10E-06 3.85E-15 3.68E-05 3.68E-05 Pu-241 4.18E-04 2.50E-14 2.69E-04 2.69E-04 Am-241 5.35E-07 3.61E-13 1.85E-05 1.85E-05 Cm-243 5.38E-07 2.61E-12 1.29E-05 1.29E-05 Ce-144 5.58E-03 3.93E-09 1.63E-04 1.63E-04 Ba-137m 1.75E-02 4.16E-07 0.OOE+00 4.16E-07 Total 9.77E-05 1.47E-02 1.48E-02

12. Acceptance Criteria(OPTIONAL)

The dose to an individual at the EAB should be less than 1 Rem integrated over the period of the radiological release. This limit is consistent with the Protective Action Guide (PAG) for the Early Release phase of an atmospheric release of I Rem defined in Section 2.3.1 of Reference 3.

729292 (Mar 2012)

Calculation Worksheet

,:9)IDoininion- ICalclatio R A-000Rv Pa g 10. of 10

13. Resuls and/orConclusions Both the 10% release and 100% release cases produce dose consequences at the site boundary that are less than the 1 Rem acceptance criteria (0.015 Rem and 0.148 Rem, respectively). These results are bounding values because each value is based on a bounding resin curie content and no decay of the resin following plant shutdown.
14. Precautionsand Limitations This calculation was prepared, reviewed, and approved in accordance with Dominion fleet procedure CM-AA-CLC-301 and GaRD CM-AA-CLC-301-1001. A Kewaunee Owner's Review of this calculation is required prior to use in accordance with Kewaunee Procedure CM-KW-REV-1 01.
15. Recommendations (OPTIONAL)

None

16. CalculationReview Checklist See Attachment 1
17. List ofAttachments Attachment I - Calculation Review Checklist Attachment 2 - Selected Pages from the Kewaunee Resin Shipment Manifest and Supporting Documentation 729292 (Mar 2012)

iwk CalculationReview Checklist jW*~ftminion C A

-A-L 30 ATAHMN 4 Pag 1 of 1 CalculationRA-0050 Rev. 0 Attachment 1 NOTE: If "Yes" is not answered, an explanation may be provided below. Reference may be made to explanations contained in the calculation or addendum.

1. Have the sources of design inputs been correctly selected and referenced in the calculation?
2. Are the sources of design inputs up-to-date and retrievable/attached to the calculation? [X] [ ]
3. Where appropriate, have the other disciplines reviewed or provided the design inputs for [X [I which they are responsible?
4. Have design inputs been confirmed by analysis, test, measurement, field walkdown, or [X I I other pertinent means as appropriate for the configuration analyzed?
5. Have the bases for assumptions been adequately and clearly presented and are they [X] [ I bounded by the Station Design Basis?
6. Were appropriate calculation/analytic methods used and are outputs reasonable when [X] I compared to inputs?
7. Are computations technically accurate? [X] [1
8. Has the calculation made appropriate allowances for instrument errors and calibration [X I I equipment errors?
9. Have those computer codes used in the analysis been referenced in the calculation? [X] [ I
10. Have all exceptions to station design basis criteria and regulatory requirements been [ [I identified and justified in accordance with NQA-1-1994?
11. Has the design authority/original preparer for this calculation been informed of its revision [X [I or addendum, if required?

Comments: (Attach additional pages if needed)

This calculation was prepared, reviewed, and approved in accordance with Dominion fleet procedure CM-AA-CLC-301 and GaRD CM-AA-CLC-301-1001. A Kewaunee Owners Review of this calculation is required prior to use in accordance with Kewaunee Procedure CM-KW-REV-101.

Reviewer's Comment During the review process, decay chains for the isotopes present in the resin were evaluated for daughter isotope contributions. It was determined that most isotopes decayed either to stable isotopes or to isotopes with half-lives >> 10,000 years. Exceptions were identified for the following daughter isotopes: Y-90, Te-125m and Pr-144.

Adding dose consequences for Y-90, Te-125m, and Pr-144 to the results presented in Tables 1 and 2 has no effect on the total dose calculated (assuming secular equilibrium and decay fractions of 1, 0.23 and 1, respectively, from their parent isotopes).

Signature: _ _ _ _ _ _ _ _ _ _ Date:

(Preparer)

Signature: __ __ _ __ __ _ Date: 9-Z-* 3 (Reviewer)

Note: Physical or electronic signatures are acceptable.

731190 (Mar 2012)

'*Q-20*ya) U.Z. NU(LF-AK KE(.ULATRKY CUIMrSJIG J. hVWm wann nsnm Lan IMCDPDK. l.lUff .. rNa, J1 AN0$4aA OkCEIP ii ~itt- In&mA~nstrmunAS DOMINION ENERGY KEWAUNEE, INC. 42913-1 NRCFORM541AND541A 2 PAGE~s) (Use*ftnuinberwiall wmlinwin page)

UNIFORM LOW-LEVEL RADIOACTIVE KEWAUNEE POWER STATION NRr P01WA 54AND~ SGA PAGE(S N490 H NAY42 ADOMOXTALINWORMSATiON -PAGE(S) SPF-IX13-01 WASTE MANIFEST KEWAUNEE.WI 54216-9511 SWIPPING PAPER I t ~ L fnMeetcc - AA....,... a eaa.. I NUllmh1 1.EMERGENCY T"EL.PHONE NUMBER (lndudeAM Co) F ,SPF-513-01 SUJeI" PrsosMn Fc"ty. LC SPFASEMtSu.;tnsn T-WZW3-L1 1920=388-831t 151T. C. Rwnlan Road DRGANIZATION Don AlIlson (Inc~ft A- Coft) ErwbflTN3785IN (423)7"*2-160 OHIFT` MANAGERrKP9 I. CARJIlER-Nwr**cIsd~m~ I (M2)388&8224 LIS THISAN EKCJJMIVE LWFSiuIPbM01d 3.TOTAL NIJASER OF Hid¶nm TrarEport SeirIcm lDArE PACKAGESIDENTIIED I560 Bear Ome ROMd Oak Pldge, TN 37830 N/A'A EP0L.NUMBER ENAO/ r 0AE =fdeof wwmanew ONTmhvlAMPP SHPPWGCA7]Z 04/rd 13 'Tf I. Ee.WWV=e WehWeift-040 tUINIWM AMISWalyCWEIMWI.L~snA poom~n. nwngo.am wbomeWc we

-~ 6 *nUr ri s.,.

TEEHN In POWnW CnJ f aupwkfnI am"En tsoV enpialw I... or"no. OrsebmadTruuPsiaWOLThisetS EPAWANFlThbNUestf

k. DOESEPAREGUIAlVD (Icaft coft WASTEREQUIRING A rl n JONt p~aet (B85p76.807 ftpW indmaiW~ Ins~mew=.f ftiIaoftOON,o.w..n ft 10CPRPus 20aM 61.0 .gjmqle w ILAX*`EST ACCMPANY N WA IIONATURE -

-a--

rThIS NPME?(r?

t?-YW.t MenA!%&IesN-b- er ~t\~ ~ DATE TT or 11 UN=32, Raio (Irk*

EPAR7AIENT OFTRANSPOFRTATION g p r shlpplng nsr.e. I~ .

and anvaddltlon:Wlonmon) rAO low SPO OMMvALPR

9.7 DESCRIPTION

UNEI nwnbee.

I 12.

DOT LABEL RADIOACTIVE YELLOW II 13.

TRANSPORT INDEX S"..

PMYSICALAND CHEMICAL V4 FORM j is.

INDVICDUAL RADIONUCLIDES C-14 Mn-,54 3M-TOTAL 1111 PACKAGE ACTIVTY INSI UNITS MB* LUA 17.

CLASS U

LSAGSCO U &

OA E~T OR VOLUME 2071*7,0Kg t!!!m 1, CTO NUMBEROF PACKAGE DOT 7A Typ A Finale EWmegid.

18-120A Cosk RQ - Raolonaum1do ~~N4 MeO 01,es Fe-5 C047 Co-8 (.8E,04 mco) 58900.0 Lbs 8-120A4 Denweted Re t9 NV" Z-45 Sr49 S-.90 tl.3.iO Le.144 Pu.ms Pe-=99 PU-241

,Xn-241 -r---- 'rc-99-LD]

(1ý429-LL0) c:i E

cu C-)

m PONLY C)

Page I of(ZPages 0

OC)

Printed on : 4/29/2013 During Shipment DOT Classification Summary Package IDNumber : 13-002 Shipment Date: 04/29/2013 Material Weight (gms): 1.99E+06 Shipment Number: SPF-0513-01 Nuclide Activity A2 I RQ LSA II (mCI) Curies Fraction Curles Fraction Fraction Co-60 6.88E+03 1.08E+01 6.37E-01

  • 1.OOE+01 6.88E-01 3.20E-07 Co-58 5.64E+03 2.70E+01 2.09E-01
  • 1.OOE+01 5.64E-01 1.05E-07 Ni-63 6.85E+04 8.10E+02 8.46E-02
  • 1.OOE+02 6.85E-01 4.25E-08 Mn-54 7.80E+02 2.70E+01 2.89E-02
  • 1.OOE+01 7.80E-02 1.45E-08 Sb-125 3.61 E+02 2.70E+01 1.34E-02 1.OOE+01 3.61 E-02 6.71 E-09 Cs-1 37 1.85E+02 1.62E+01 1.14E-02 1.00E+00 1.85E-01 5.73E-09 Ce-144 5.58E+01 5.40E+00 1.03E-02 1.OOE+00 5.58E-02 5.19E-09 Fe-55 5.28E+03 1.08E+03 4.89E-03 1.OOE+02 5.28E-02 2.45E-09 Pu-241 4.18E+00 1.62E+00 2.58E-03 1.OOE+00 4.18E-03 1.30E-09 Co-57 4.05E+02 2.70E+02 1.50E-03 1.OOE+02 4.05E-03 7.53E-10 Zn-65 7.08E+01 5.40E+01 1.31 E-03 1.OOE+01 7.08E-03 6.59E-10 Pu-238 1.63E-02 2.70E-02 6.05E-04 `1.00E-02 1.63E-03 3.04E-10 C-14 4.26E+01 8.10E+01 5.26E-04 1.OOE+01 4.26E-03 2.64E-10 Pu-239 1.10E-02 2.70E-02 4.06E-04 1.00E-02 1.10E-03 2.04E-10 Sr-90 3.24E+00 8.1 OE+00 4.OOE-04 1.OOE-01 3.24E-02 2.01E-10 Cm-243 5.38E-03 2.70E-02 1.99E-04 1.OOE-02 5.38E-04 1.00E-10 Am-241 5.35E-03 2.70E-02 1.98E-04 1.OOE-02 5.35E-04 9.95E-11 Sr-89 5.44E-01 1.62E+01 3.36E-05 1.OOE+01 5.44E-05 1.69E-11 H-3 1.77E+01 1.08E+03 1.64E-05 1.00E+02 1.77E-04 8.24E-12 Ni-59 5.64E+02 No A2 0.OOE+00 1.00E+02 5.64E-03 0.OOE+00 Sums: mCi: 8.88E+04 Type A: 1.01 E+00 RQ: 2.41E+00 LSA: 5.06E-07 Compare LSA Fraction to LSA II (solid) limit of <= 1 E-4
  • Nuclides included in 95% of the hazard fraction as per 49 CFR 173.433(g) Page 9 of ILPages
Retrieved from "https://kanterella.com/w/index.php?title=ML14029A066&oldid=2454063"