ML060750758

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Enclosure 2, Calculation N-4072-001, Rev 6, CCN-9 Fuel Handling Accident Inside Fuel Handling Building Control Room & Offsite Doses
ML060750758
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 01/21/2006
From: Drucker M, Remick T
Southern California Edison Co
To:
Office of Nuclear Reactor Regulation
References
CCN-9 N-4072-001, Rev 6
Download: ML060750758 (25)
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ENCLOSURE 2  :

.1 E'CALCULATION N-4072-001 CCN-9 l FUEL' HANDLING ACCIDENT INSIDE FUEL HANDLIM IG BUILDING -

' CONTROL 'ROOM & OFFSITE DOSES . r 4 -  !

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Scuthern Calltornia Edison Company CALC NO. EON NO./ PAGE TOTAL NO. OF ENGINEERING CHANGE N.4072-001 PRLIM CON NO. N-8 1 PAGES 24 NOTICE (ECNY CALCULATION CHANG3E NOTICE EASE CALC. REV. UNIT CCN CONVERSION CALC. REV.

(CCN) COVER PAGE 6 2 & 3 CCN NO. CCN-

SUMMARY

CHANCE CD NODY GES CALCULATION

SUBJECT:

Fuel Handling Accident Inside Fuel Handling Building -

NO El YEs Control Room & Offsite Doses CALCULATION CROSS-INDEX ENGINEEnING SYSTEM NUMB3ERFPRIMARY STATION SYSTEM O-CLASS 0 New/Updated index Induded DESIGNATOR 1504 &l1 / GGA and GKA II n Existing Index Is Complete CONTROLLED PROGRAM OR I S0 °_PROGRAM/DATABASE NAME(S) VERSION/RELEASE ND IS)

Sile Programs/Procedure Impad? DATABASE ACCORDING TO 0 ALSO. LISTED BELOW SO123-XXIV-5.1 NO O YEs, AR No. . PROGRAM 0 DATABAS E 1cICFRso.59fl2.41 Revieyr. N/A N/A AR No. 040700770-08 _ .

1. BRIEF DESCRIPTION OF ECN/CCN Appendix A is revised to evaluate the radiological consequences at the Exclusion Area Boundary due to the drop of a transfer cask containing 24 Unit 2 (or Unit 3) fuel assemblies irto the cask pool of the Unit 2 (or Unit 3) Fuel Handling Building. The drop is assumed to occur prior to the transfer cask being welded closed. Appendix A retains its similar evaluation evaluating the drop of a transfer cask containing 24 Unit 1 fuel assemblies into the cask pool of either the Unit 2 or Unit 3 Fuel Handling Buldings.

Pages Revised: 7, 14, 250 through 261 Pages Added: 262 through 270 Pages Deleted: None INITIATING DOCUMENT(ECP, OTHER) AR 040700770-07 Rev. N/A

2. OTHER AFFECTED DOCUMENTS; YES ° NO OTHER AFFECTED DOCUMENTS EXIST AND ARE IDENTIFIED ON ATTACHED FORM 26-503.
3. APPR OE ESC. N/A MARK RUCKER (POS T2RE42 & T3EN64) _ t ORIGINATOR (Print narne/sign/date) FLS ate)

Appr re ires POS T3EN54 Qualiticatv.n Veritied: V 7

Approval requires P T3EN64 6 &

Oualification Verilied.

Initial Initial TOM REMICK (POS T2RE42 & T3EN64)

IRE (Print name/sign/date)

Approval requires POS T3EN64 Oualifrcal ion Verilied:

Inhitia

4. CONVERSIONTOCCNDATE /// 6 S C...MSONGs SCE26-122-1 REV 9 IREFERENCE SO123-XXIV-7.151 LI' Site File Copy N-4072-001

CALCULATION CROSS-INDEX ECN NOJI PRELIM. CCN NO. N-8 IPAGE 2)F 2_LJ I

Calculation No. N-4072-001 Sheet 7 of 270 I.

CCN CONVERSION, CCN NO. CCN- q INPUTS OTUSDoes the Calc. rev. These interfacing calculations and/or Rcsults and conclusions off tethe ssubjectt output interface interface number documents provide input to the subject calculation are used in these interfacing calc/document calc/document and calculation, and if revised may require calculations and/or documents. require responsible rovision of the subject calculation. revision CCN, ECP, TCN/Rev., or FLS initials tracking number and date Calc/Documant No. Rev. No. Calc/Document No. Rev. No. YES/NO Rev. 6 Procedure S023-X-7 10 Procedure S023-X-7.2 6 AOl S023-13-20 . . 7 Unit I Calculation DC-3782 0

& CCN 1 Calculation SNM-DBASE-1 1 11 Unit 2 Calculation NFM-2-PH-1216 0 Unit 3 Calculation NFM-3-PH-1216 0 CCN N-8 SO1-207-1-M210 2 UFSAR2/3-15.10 32 YES AR 040700770 - 18 (Section 15.10.7.3.5)

RGR-U2/3-C14 I DBD-SO23-TR-AA 7 YES ECN # A40767

{fr ______ (Section 4.3.17) 11o~ .________________ I______ I_____I_____I_____I__

SCE 26.424 RfEV. 6 CREPWEfNCE S0123.XXXIV-7.15]

E&TS DEPARTMENT .

ECN NO.1 NO. l CALCULATION SHEIET IPRELIM. CCN NO. N-5 I PAGEŽ?~OF '1'A I Project or ECP CaIc. No. N-4072-001 CCN CONVERSION:

I CCN NO. CCN -- 9 Subject Fuel HandlinQ Accident Inside Fuel Handling Building - CR & Offste Doses Sheet 14 of 270 REVl ORIGINATOR l DATE E ATE REV ORIGINATOR DATE IRE DATE R 6 N.YACKLE T. REMICK l l M. DRUCKER T. REMICK l For conservatism this calculation does not credit FHB airborne iodine and particulate activity removal by Post Accident Cleanup (PACU) Filter Units S2(3)1504tvE370 or S2(3)1504ME37 1.

Table 2.1-1 Fuel Handling Accident Inside the Fuel Handling Building Doses Location j Criteria (Rem) j Dose (Rem)

Control Room (event duration dose) 10 CFM 1000 CFM

[CR isolated at 3 minutes] CRUnfiltered In- CR Unfiltered hi-leakage leakage 3438 MWt 3438 MWt 1.72 Radial 1.75 Radial Peaking Peaking Thyroid Inhalation 30 .

Beta Skin Immersion 30 5.6 9.3 Whole Body Gamma Immersion and 5 1.2 1.2 Shine <0.1 <0.1 EAB (2-hour dose)

Thyroid Inhalation 75 18.4 18.8 Beta Skin Immersion no dose criterion 0.1 0.1 Whole Body Gamma Immersion and 6 < 0.1 <0.1 Shine LPZ (event duration dose)

Thyroid Inhalation 75 0.5 0.5 Beta Skin Immersion no dose criterion < 0.1 <0.1 Whole Body Gamma Immersion and 6 < 0.1 <0.1 Shine The EAB dose consequences of a transfer cask drop in the Units 1, 2 or 3 cask loading area are I presented in Appendix A. The transfer cask can be loaded with up to 24 Unit 1, 2 or 3 spent fuel I assemblies.

I-N-4072-001

E&TS DEPARTMENT ECN NOJ I 1 CALCULATION SHEET PRELIM. CCN NO. N- I PAGE I OF 2q Project or ECP CaIc. No. N-4072-001 - CCN CONVERSION, I CCN NO. CCN -- 9 Subject Fuel Handling Accident Inside Fuel Handling Building - CR & Offsite Doses Sheet 250 of 270 REVIN ORGIATORE DAT IREMC DATE REV ORIGINATOR DATE IRE jDATE R 6 IN. YACKLE T. REMICK v IM. DRUCKER T.REMICK l A1.0 PURPOSE A1.1 Task Description The purpose of this Appendix is to assess the dose consequences of a transfer cask drop in the Unit 1 Spent Fuel Building cask loading area, or a transfer cask drop in the cask pool of either the Unit 2 or Unit 3 Fuel Handling Building. A transfer cask drop is currently not postulated to occur in the Unit I spent fuel pool area because a single failure proof crane will be used for all lifts. The Unit 1 calculation is included for completeness. Even though single failure proof cranes will be used at Units 2 and 3 to lift the transfer cask out of the cask pools, a drop can be postulated when the cask is placed on the upper shelf (i.e., step) of the cask pool for lifting yoke change-out, prior to the transfer cask being welded closed. During this evolution, the cask is not restrained and could fall back into the lower portion of the cask pool if an earthquake occurs.

The fuel rods from all 24 Unit 1 or Units 2/3 fuel asseniblies that may be present in a transfer cask are conservatively assumed to rupture on cask impact with the bottom of the pool. All the radioactive iodine and noble gas remaining in the fuel rod gap volume are expected to be released from the unwelded transfer cask.

The evaluation to assess the dropping of a transfer cask containing Units 2/3 fuel assemblies provides closure for AR Assiginment 040700770-07.

A1.2 Dose Acceptance Criteria Standard Review Plan (SRP) 15.7.5 (Reference A6.2e, Section I1.L) states that the radiological consequences of a postulated spent fuel cask drop accident are acceptable if the calculated whole-body and thyroid doses at the exclusion area boundary (EAB) and low population zone (LPZ) outer boundary are "well within" the exposure guideline values of 10 CFR Part 100, paragraph 11 (i.e., 300 rem for the thyroid and 25 rem for the whole-body doses). Per SRP 15.7.5, "well within" means 25 percent or less of the 10 CFR Part 100 exposure guidelines. Per SRP 15.7.5, these "well within" guideline values are 75 rem for the thyroid dose and 6 rem for the whole-body dose. SRP 15.7.5 does not specify a beta-skin dose criterion.

Per Section A5.0, this analysis conservatively models a puff release of activity to the environment. In this model, the sole difference between the exclusion area boundary (EAB) and low population zone (LPZ) doses would be in the modeling of the EAB and LPZ atmospheric dispersion factors (X/Qs). Per Design Input 4.7, the 0 to 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> EAB X/Q is approximately two orders of magnitude greater than the 0 to 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> LPZ X/Q. Therefore, the EAB doses will be approximately two orders of magnitude greater than the LPZ doses. Since the EAB and LPZ have the same dose acceptance criteria, this analysis will only evaluate the radiological consequence at the EAB.

N-4072-001

E&TS DEPARTMENT 1

CALCULATION SHEET I ECN NOJ MPAGE OF20`

Project or ECP Caic. No. N-4072-001 lI CCN CONVERSION, CCN NO. CCN - 9 Subject Fuel Handling Accident Inside Fuel Handling Wuilding - CR & Offsite Doses Sheet 251 of 270 REVl ORIGINATOR l DATE l IRE l DATE lREV ORIGINATOR DATE IRE DATE R 6 IN. YACKLE T REMICK IIv M. DRUCKER T. REMICK I A2.0 RESULTS/CONCLUSIONS AND RECOMMENDATIONS A2.1 Dropping of a Transfer Cask Containing 24 Unit 1 Fuel Assemblies That Have Decayed for 10 Years The EAB whole body gamma doses due to a transfer cask drop in the Unit I Spent Fuel Building, or a transfer cask drop in the Unit 2 or Unit 3 Fuel Handling Buildings (FHBs) are 0.0094 rem (i.e., < 0.1 rem) and 0.0027 rem (i.e., < 0.1 rem), respectively. The thyroid dose is zero, since all the iodine isotopes have decayed to zero. The whole body gamma and thyroid doses are small compared to the EAB dose criteria specified in Section Al .2, and are less severe than those of the design basis fuel handling accident in the fuel handling building (FHA-FHB) as reported in Section 2.1 Table 2.1-1 (based on the results presented in Section 8.11, Table 8.11-a).

The EAB beta skin doses for a transfer cask drop at Unit I and Units 2/3 are 0.78 rem and 0.22 rem, respectively. These beta skin doses exceed the 0.1 rem design basis FHA-FHB dose reported in Section 2.1 Table 2.1-1. However, as noted in Section A1.2, there is no EAB beta skin dose criterion for a fuel handling accident. Therefore, the EAB beta skin dose need not be documented in the UFSAR or Accident Analysis DBD.

A2.2 Dropping of a Transfer Cask Containing 24 Units 2/3 Fuel Assemblies That Have Decayed for 5 Years The EAB doses due to the dropping of a transfer cask in the Unit 2 or Unit 3 Fuel Handling Building (FHB) containing 24 Units 2/3 fuel assemblies that have decayed for 5 years are calculated in Sections A8.5 through A8.7. Due to the inherent uncertainties in any dose analysis, the results are rounded up to the nearest 0.1 remn Doses less than 0.1 rem are reported as such.

The EAB whole body gamma dose due to a transfer cask drop in the Unit 2 or Unit 3 FHB is 0.0045 rem (i.e., < 0.1 rem). The wholebody gamma dose meets the EAB 6 Rem dose criterion specified in Section A1.2, and is less severe than that of the design basis FHA-FHB as reported in Section 2.1 Table 2.1-1 (based on the results presented in Section 8.11, Table 8.11-1 a).

The EAB thyroid dose due to a transfer cask drop in the Unit 2 or Unit 3 FHB is 0.046 rem (i.e., < 0.1 rem).

The thyroid dose meets the EAB 75 rem dose criterion specified in Section A1.2, and is less severe than that of the design basis FHA-FHB as reported in Section 2.1 Table 2.1-1 (based on the results presented in Section S.11, Table 8.11-la).

The EAB beta skin doses for a transfer cask drop in the Unit 2 or Unit 3 FHB is 0.373 rem (i.e., rounded up to 0.4 rem). This beta skin dose exceeds the 0.1 rem design basis FHA-FHB dose reported in Section 2.1 Table 2.1-1. However, as noted in Section AI.2, there is no EAB beta skin dose criterion for a fuel handling accident. Therefore, the EAB beta skin dose need not be documented in the UFSAR or Accident Analysis DBD.

N-4072-001

E&TS DEPARTMENT ECN NOJ I n' CALCULATION SHEET PRELIM. CCN NO. N-8 I PAGE ( OF ]

Project or ECP Caic. No. N-4072-001 CCN CONVERSION' CCN NO. CCN -- _

Subject Fuel Handling Accident Inside Fuel Handling Building - CR & Offsite Doses Sheet 252 of 270 REVl ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 6 N. YACKLE IT.REMICK _ V M. DRUCKER T. REMICK =

A3.0 MODELING ASSUMPTIONS A3. 1 All fuel rods in the 24 assemblies loaded into the canister inside the transfer cask are conservatively assumed to be intact when they are loaded. All the fuel rods are then assumed to rupture as a result of the cask drop.

A3.2 All of the radioactive material released into the Fuel Storage/Fuel Handling Building atmospheres is assumed to be instantaneously released to the outside environment as a puff release. The dose received at the exclusion area boundary (EAB) for a puff release is the same as the integrated dose for a two hour release.

A3.3 A rrnirnum of 10 years has elapsed since permanent discharge from the core for all Unit 1 fuel assemblies that are loaded into the canister/transfer cask. I I

A3.4 A minimum of 5 years has elapsed since permanent discharge from the core for all Units 2 & 3 fuel I assemblies that are loaded into the canister/transfer cask. This minimrnum decay time is consistent I with the Certificate of Compliance for the Units 2/3 Spent Fuel Storage Cask 24PT4-DSC I (Reference A6.2c, Section 2.2.c). I N-4072-001

E&TS DEPARTMENT CALCULATION SHEET PE Project or ECP CaIc. No. N-4072-001 Subiect Fuel Handlina Accident Inside Fuel Handlina Buildina - CR & Offsite Doses Sheet 253 of 270 REV ORIGINATOR 6 N. YACKLE

-

MDRUCKER I

l Y

DATE l

l IRE J T. REMICK[

T. EMIK l DATE REV R

ORIGINATOR IN T DATE T j IRE I

DATE D

R A4.0 DESIGN INPUTS A4.1 The Unit I spent fuel pool contains all assemblies off-loaded subsequent to shutdown at the end of Unit I Cycle 11. End of Cycle II shutdown occurred on November 30, 1992 (Reference A6.2a).

All fission gases in the spent fuel rods in the Unit I spent fuel pool have therefore decayed for a minimum of 10 years prior to the earliest estimated removal from the spent fuel pools which will occur no earlier than January, 2003.

Per Reference A6.2a, the most recently off loaded Unit 1 spent fuel assembly stored in the Unit 2 spent fuel pool is Assembly G029. It was permanently discharged at the end of Unit I Cycle 8 (November 21, 1985).

Per Reference A6.2a, the most recently off loaded Unit 1 spent fuel assemblies stored in the Unit 3 spent fuel pool were permanently discharged at the end of Unit I Cycle 10 (June 30, 1990).

The Unit I assembly with the highest burnup is located in the Unit I spent fuel pool (Reference A6.2a). Since the Unit I spent fuel pool contains the highest burned assembly, and the assemblies which have been stored the shortest time since reactor shutdown, the source terms for Unit I fuel in the Unit I pool bound the source terms for Unit 1 assemblies stored in either the Unit 2 or Unit 3 spent fuel pools.

A4.2 Per Reference A6.la, Table 1, Column 5, Unit I assembly iodine and noble gas radioisotope inventories at reactor shutdown (no decay) are shown in Table A4.1.

Table A4.1 Assembly Iodine and Noble Gas Inventories at Reactor Shutdown

=-

ISOTOPE l ACTIVITY (A,)

= (ci/assy) 1-131 251600 1-132 339500 1-133 468200 1-134 526100 1-135 453500 Xe-131m 2650 I-N-4072-001

E&TS DEPARTMENT ECN NOJ l 8 v CALCULATION SHEET l PRELIM. CCN NO: N-8 I PAGE__ OF _

Project or ECP Cac. No. N-4072-001 CCN CONVERSION CCN NO. CCN -- 9 Subject Fuel Handling Accident Inside Fuel Handlina Buildina - CR & Offsite Doses Sheet 254 of 270 REi ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE l IRE DATE R N. YACKLE M T. REMICK v L IM. DRUCKER T. REMICK _

ISOTOPE ACTIVITY (AO)

(ci/assy)

Xe-133m 12700 Xe-133 586600 Xe-135m 140100 Xe-135 189800 Xe-137 437600 Xe-138 435700 Kr-83m 36940 Kx-85m 87900 Kr-85 5120 Kr-87 186600 Kr-88 235000 Kr-89 341400 A4.3 Per Reference 6.4i, Section C.ld, all of the gap activity in the damaged Unit 1 fuel rods is released I from the damaged fuel rods. This gap activity consists of 10 percent of the total noble gases other than Krypton-85, 30 percent of the Krypton-85, and 10 percent of the radioactive iodine in the rods at the time of the accident.

A4.4 The decay constants for the all isotopes listed in Table A4.1 are shown in Table A4.2. The values for al isotopes are taken from References 6.6a (Theoretical Manual).

N-4072-001

E&TS DEPARTMENT ECN NOJ 9IP i CALCULATION SHEET PRELIM. CCN NO. N-5 PAGE-L-OF>l Project or ECP Calc. No. N-4072-001 CCN CONVERSION:

CCN NO. CCN -- q Subject Fuel Handling Accident Inside Fuel Handling E3uilding - CR & Offsite Doses Sheet 255 of 270 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 6 N. YACKLE T. REMICK =v

_ M. DRUCKER T. REMICK _

Table A4.2 Isotopic Decay Constants ISOTOPE - DECAY CONSTANT (1)

L_ I(sec)'

1-131 0 1-132 0.0000843 1-133 0.000009 1-134 0.00022 1-135 0.0000291 Xe-131m 0 Xe-133m 0.000004 Xe-133 0.000002 Xe-135m 0.000738 Xe-135 0.0000212 Xe-137 0.003024 Xe-138 0.0008151 Kr-83m 0.0001052 Kr-85m 0.000043 Kr-85 0 Kr-87 0.0001514 Kr-88 0.0000673

= Kr-89 0.003632 I.-

N-4072-001

E&TS DEPARTMENT CALCULATION SHEET Project or ECP Calc. No. N-4072-001 Subject Fuel Handlina Accident Inside Fuel Handlina Buildina - CR & Offsite Doses Sheet 256 of 270 IREV ORIGINATOR IDATE l IRE IDATE IREVI ORIGINATOR IDATE I IRE 1DATE R l 6 N.YACKLE T.REMICK D V lM. DRUCKER T. REMICK =

A4.5 Per Design Input 4.8, the Kr-85 thyroid inhalation dose conversion factor (DCFhy) is 0.0 rem/curie, dte Kr-85 beta skin. immersion dose conversion factor (DCFbi;) is 4.246E-02 rem-m 3/curie-sec, and the Kr-85 whole body gamma immersion dose conversion factor (DCFWbgt) is 5.102E-04 rem-m3/curie-sec.

Per Design Input 4.8, the 1-129 thyroid dose conversion factor is 5.92E+06 rem/curie, the 1-129 beta-skin immersion dose conversion factor is 3.71 OE-04 rem-n?/curie-sec, and the 1- 129 whole body gamma immersion dose conversion factor is 3.024E-03 rern- 3 /curie-sec.

A4.6 Per Design Input 4.7, the exclusion area boundary (EAB) atmospheric dispersion factor (X/Q) is 2.72E-04 sec/rn3 for the Units 2/3 Fuel Handling Buildings.

A4.7 Per Reference A6.Ia, Design Input 2, the exclusion area boundary (EAB) atmospheric dispersion factor (X/Q) is 9.50E-04 sec/rn3 for the Unit I Fuel Storage Building.

A4.8 Per Design Input 4.1.1, all of the gap activity in the damaged Units 2 & 3 fuel rods is assumed to be released from the damaged fuel rods. Per Design Input 4.1.2, this gap activity consists of 10 percent of the total noble gases other than Krypton-85, 30 percent of the Krypton-85, and 12 percent of the radioactive iodine in the rods at the time of the accident.

A4.9 Per Design Analysis NFM-2/3-PH-1 116 (Reference 6.1 aa, Section 4.3 and its referenced Table 3.3-1), the Units 2 & 3 single fuel rod radioisotope iodine and noble gas inventory five years after reactor shutdown is:

Iodine-129 1.2013-04 curies/rod Krypton-E5 1.90E+01 curies rod All other iodine and noble gas isotopes O.OOE+00 curies/rod Design Analysis NFM-2/3-PH- 116 documents the presence of tritium in an average fuel rod five years after reactor shutdown. However, per Design Input 4.1.1 tritium is not considered in this analysis since Regulatory Guide 1.25 Section C.Id does not require consideration of non-iodine or non-noble gas gap activity releases from damaged fuel rods.

A4.10 Each Unit 2 or Unit 3 fuel assembly contains 236 fuel rods (Reference A6.2d, Item Xl.006).

A4.11 Per Assumption 3.10, the EAB breathing rate is 3.47E-04 a 3 /sec.

N-4072-001

E&TS DEPARTMENT ECN NOJ tt 2 CALCULATION SHEET IPRELIM. CCN NO. N-a I PAGE OF_

Project or ECP Cabc. No. N-4072-001 CCN CONVERSION:

I CCN NO. CCN -- 4 Subject Fuel Handling Accident Inside Fuel Handling 3uilding - CR & Offsite Doses Sheet 257 of 270 REV ORIGINATOR DATE IRE DATE I REV ORIGINATOR 1 DATE IRE DATE R 61N. YACKLE _ T. REMICK _ Iv M. DRUCKER T. REMICK 4 A5.0 METHODOLOGY All calculations in this Appendix were completed using a spread sheet, or were done by hand using a calculator. The Unit I iodine and noble gas radioisotope 10-year decayed assembly inventories I were calculated using tht following equation for radioactive decay (Reference A6.2b):

A=Ao e v Where A = Inventory of isotope A at time t (ci)

Ao = Inventory of isotope A at time t = 0 (ci)

X. = decay (transformation) constant of isotope A (sec')

t = elapsed time (sec)

The preceding equation is not required when evaluating the dropping of a cask loaded with Unit 2 or 3 fuel.

Design Input A4.9 presents the Units 2 & 3 iodine and noble gas radioisotope 5-year decayed fuel rod inventories.

I Since a puff release is assumed for thiis calculation, the beta skin, whole body and thyroid doses received at the EAB for each isotope is given by the following equation:

Dbi or Dbgi == AR A/Q*

  • DCF I Dthy = AR
  • X'Q
  • BR
  • DCFhy I I

Where I D = Dose (beta skin imnersion, whole body gamma immersion or thyroid) (rem)

AR = Inventory released for each isotope (ci)

X/Q = Atmospheric dispersion factor (sec/n?)

DCF = Dose Conversion Factor (beta skin immersion or whole body gamma immersion)

(rem-rfm3 /ci -sec) I I

DCF,hy = Dose Conversion Factor (thyroid inhalation) (rem/ci) I I

BR = Breathing Rate at the EAB (m3 /sec) I I

I I-N-4072-001

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I CCN NO. CCN -- 1 -

Subject Fuel Handling Accident Inside Fuel Handling Building - CR & Offsite Doses Sheet 258 -of 270 REVl ORIGINATOR l DATE IRE DATE lREV ORIGINATOR DATE IRE j DATE R 6 N. YACKLE T. REMICK v

-M. DRUCKER T. REMICK =

The preceding equations are adapted from Reference 6.6a, Section 4.3; terms that are not applicable for a puff release are eliminated.

The inventory released for each isotope is given by the following equations: I I

A(asanbly) =ANrod)

  • N(TOd) I I

AR = A(aSsembIy)

  • f2
  • f Where A(sely) = Assembly decayed inventory (ci/assy)

A(rod) = Single Fuel Rod decayed inventory (ci/rod) I I

N(rod) = Numnber of fuel rods per assembly (rod/assy) I n = Number of assemblies in cask (assy) f = gap fraction (unitless)

I-N-4 072-0 01

E&TS DEPARTMENT CALCULATION SHEET ECN NOJ PRELIM.CCNNO. N lPAGEI30F F

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Project or ECP Calc. No. N-4072-0O1 CCN CONVERSION:

CCN NO. CCN -- 7 Subject Fuel Handling Accidant Inside Fuel Handling Building - CR & Offsite Doses Sheet 259 of 270 REVY ORIGINATOR MN.YACKLE M. DRUCKER DATE E T. REMICK

_T. REMICK DATE REV ORIGINATOR I DATE IRE DATE Iv R

4 A6.0 REFERENCE'S A6.1 Calculations A6.1a SONGS Unit 1 C(alculation No. DC-3782, Revision 0, "SONGS I E-Planning Doses Due to Fuel Handling Accident", dated 10o29/92, including CCN No. I dated 06/02/94.

A6.2 Other Documents A6.2a SNM-DBASE-10, Software Installation Report, "Special Nuclear Material Database", dated 05105/99; Appendix C Excerpt including the data base listing for Unit 1.

A6.2b Cember, Herman, "Introduction to Health Physics", Second Edition, Pergarnon Press, 1989.

A6.2c Document SO1-207-1-M210, Revision 2,"ISFSI Certificate of Compliance for Spent Fuel Storage Casks - Technical Specifications for the Advanced NUHOMS System Operating Controls and Limits".

A6.2d Docurnent RGR-U2/3-C14, Revision 1,"SONGS Units 2/3 Cycle 14 Reload Ground Rules".

A6.2e NUREG-0800, Standard Review Plan 15.7.5, Revision 2, "Spent Fuel Cask Drop Accidents",

July 1981.

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I CCN NO.CCN - I, Subject Fuel Handling Accident Inside Fuel Handling Building - CR & Offsite Doses Sheet 260 of 270

!REVI ORIGINATOR DATE I RE DATEI REV ORIGINATOR DATE IRE DATE [R IM.DRUCKER T. REMICK A7.0 NOMENCLATURE EAB exclusion area boundary A, Inventory of isotope A at time t = 0 (ci)

X decay (transformation) constant of isotope A (sec-')

DCF dose conversion factor DCFbi~ dose conversion factor, beta skin immersion (rem-m 3/curie-sec) 3 DCF.1b, dose conversion factor, whole body gamma immersion (rem-r /curie-sec)

DCFdY dose conversion factor, thyroid inhalation (rem/ci)

BR breathing rate at the EAB (rn 3/sec)

X/Q atmospheric dispersion factor (sec/r 3 )

A Inventory of isotope A at time t (ci) t elapsed time (sec)

D Dose (beta skin immersion, whole body gamma immersion, or thyroid) (rem)

AR Inventory released for each isotope (ci)

A(=asibly) Assembly decayed inventory (ci/assy)

Ai.d) Single Fuel Rod decayed inventory (ci/rod) n Number of assemblies in cask (assy)

N(rod) Number of fuel rods per assembly (rod/assy) f gap fraction (unitless)

Dwbt whole body gamma immersion dose (rem)

Db5 i beta skin irnmersion dose (rem)

D~hy thyroid inhalation dose (rem)

I-N-4072-001

E&TS DEPARTMENT CALCULATION SHEET [E Project or ECP Caic. No. N-4072-001 Subject I=

Fuel Handlina Accident Inside Fuel Handlina EBuildinq - CR & Offsite Doses Sheet 261 of 270 REVl ORIGINATOR DATE l IRE l DATE REV ORIGINATOR DATE IRE DATE R

_N. YACKLE = _T. REMICK =E==l = v L M. DRUCKER T. REMICK _

assy assembly ci curie sec second m meter N-4 072- 001

E&TS DEPARTMENT .

ECNNOJN11 1 CALCULATION SHEET PRELIM. CCN NO. N-8 PAGE OF lj Project or ECP Calc. No. N-4072-001 CCN CONVERSION:

CCN NO. CCN -- q Subject Fuel Handling Accident Inside Fuel Handling Building - CR & Offsite Doses Sheet 262 of 270 IREV ORIGINATOR DATE IRE l DATE REV ORIGINATOR DATE IRE DATE R 6 N. YACKLE T. REMICK V M. DRUCKER T. REMICK _ .

A8.0 CONMPUTATIONS The Unit I iodine and noble gas radioisotope assembly inventory 10 years after reactor shutdown are I calculated in a spread sheet using the equation for radioactive decay provided above. The results are shown in Table AS.1.

TABLE A8.1 Unit 1 Iodine and Noble Gas Assembly Inventory I 10 Years After Reactor Shutdown ISOTOPE UNIT 1 ASSEMBLY ACTIVITY (Aamssnbly))

(ci/assy) 1-131 0 1-132 0 1-133 0 1-134 0 1-135 0 Xe-13lm 0 Xe-133m 0 Xe-133 0 Xe-135m 0 Xe-135 0 Xe-137 0 Xe-138 0 Kr-83m 0 Kr-85m 0 Kr-85 2679 Kr-87 0 N-4072-001

E&TS DEPARTMENT CALCULATION SHEET I NOJ EC.

I IM. CCN NO. N-8 _IPAGE AGLOF_

OF _I Project or ECP CaIc. No. N-4072-001 CCN CONVERSION: <

- I CCN NO. CCN --

Subjec1 Fuel Handling Accident Inside Fuel Handling 3uilding - CR & Offsite Doses Sheet 263 of 270 REVl RIGINATOR DATE IRE DATE l REVl ORIGINATOR DATE IRE DATE R 6 N. YACKLE T. REMICK v M. DRUCKER _T. REMICK 4 ISOTOPE UNIT I ASSEMBLY ACTIVITY (Atasseffbly))

_ (ci/assy)

Kr-88 0 Kr-89 0 Since all Unit I iodine isotopes and all noble gas isotopes except Kr-85 have decayed to zero after 10 years of decay, only the beta skin and whole body immersion doses due to Kr-85 are calculated.

The Units 2&3 iodine and noble gas radioisotope assembly inventory 5 years after reactor shutdown are calculated in Table A8.2 by the following equation introduced in Section A5.0. As a sample calculation, the Units 2 and 3 assembly Krypton-85 activity after 5 years of decay is:

Nassemabiy) = (Arod)' N (rod) = (1 9.0 ci/rod) * (236 rods/assy) = 4.484E+03 ci/assy TAB-LE A8.2 Units 2&3 Iodine and Noble Gas Assembly Inventory 5 Years After Reactor Shutdown ISOTOPE UNITS 2&3 FUEL RODS PER UNITS 2&3 I FUEL ROD UNITS 2&3 ASSEMBLY I ACTIVITY FUEL ASSEMBLY ACTIVITY I AT 5 YEARS AT 5 YEARS I IAssumption A3.4] [Design Input A4.10] I I _(ci/rod) (rods/assy) (ci/assy) I 1-129 1.20E-04 l 236 2.832E-02 I KR-85 1.90E+01 l 236 4.484E+03 I I-N-4 072-001

E&TS DEPARTMENT . .

ECN NOJ I c 2 CALCULATION SHEET PRELIM. CCN NO. Na I PAGEL) OF i Project or ECP Calc. No. N-4072-OO1 - CCN CONVERSION: (

I CCN NO. CCN -- 2 Subject Fuel Handling Accident Inside Fuel Handling Building - CR & Offsite Doses Sheet 264 -of 270 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 6 N.YACKLE T.REMICK R= E M. DRUCKER T. REMICK 4 A8.1 Dropped Cask of Unit 1 Fuel in the Unit 1 Fuel Building, Unit I EAB Whole Body Gamnma I Immersion Dose Per Table A8.1 above, Assumption A3.1 and Design Inputs A4.3, A4.5 and A4.7:

A(,S,,aly),=Assembly decayed inventory = 2.679E+03 ci/assy n =Number of assemblies in cask = 24 assy f =gap fraction = 30%/100% = 0.30 x/Q =9.50E-04 sec/m3 DCFwbg; =5.102E-04 re-m 3 /curie-sec.

And Dxbli = A

  • X/Q
  • DCFbg, Dwby; = A(assmbly)
  • n
  • f
  • X/Q
  • DCFbgi D~b,; = 2.679E403 ci/assy *24 assy*0.30*9.50E-04 sec/m 3*5.102E-04 rernm-/curie-sec Dwb; = 9.35E-03 rem NK I.-

N-4 072-001

E&TS DEPARTMENT ECN NOJ CALCULATION SHEET PRELIM CCNNO N- IPAGE 92 OF2L Project or ECP CaIc. No. N-4072-001 CCN CONVERSION:fl I CCN NO. CCN --

Subject Fuel Handlinq Accident Inside Fuel Handling EBuildin - CR & Offsite Doses Sheet 265 of 270 REV ORIGINATOR DATE IRE DATE REVI ORIGINATOR DATE IRE DATE R 6 N YACKLE T. REMICK l I T I v l M.DRUCKER I T. REMICK I A8.2 Dropped Cask of Unit 1 Fuel in the Unit I Fuel Building, Unit 1 EAB Beta Skin Immersion Dose Per Table A8. 1 above, Assumption A3.1 and Desig n Inputs A4.3, A4.5 and A4.7:

A(asbl~y)=Assemb)ly decayed inventory =2.679E+03 ci/assy n =Number of assemblies in cask =24 assy f =gap fraction = 30%/100% =0.30 XIQ =9.50E-04 sec/n 3 DCFbSi =4.246E-02 rem-m 3 /curie-sec.

And, DbSi = A

  • X/Q
  • DCFbSI Dbi = A.,.mbly)
  • nf
  • X/Q
  • DCFb5 ;

Db,1 = 2.679E+03 ci/assy *24 assy*0.30*9.50E-04 sec/m3 *4.246E-02 rem-mn/curie-sec D,;= 7.77E-01 rem I-N-4072-001

E&TS DEPARTMENT PRELIM. CCN NO. N-B __FP CALCULATION SHEET ECN NOJ N PAGE'C-'OF 2l Project or ECP Cac. No. N-4072-001 CCN CONVERSION:

ICCN NO. CCN -- 1 Subject Fuel Handling Accident Inside Fuel Handling Building - CR & Offsite Doses Sheet 266 of 270 REV 1 ORIGINATOR DATE ITRE DATE REV ORIGINATOR DATE IRE DATE R N. YACKLE M T. REMICK v M. DRVCKER T. REMICK _

A8.3 Dropped Cask of Unit I Fuel in the Unit 2 or 3 Fuel Handling Building, Unit 2/3 EAB Whole Body Gamma Immersion Dose Per Table A8.1 above, Assumption A3.1 and Design Inputs A4.3, A4.5 and A4.6:

At..bly) = Assembly decayed inventory = 2.679E+03 ci/assy n =Numnber of assemblies in cask = 24 assy f =gap fraction = 30%/100% 0.30 X/Q =2.72E-04 sec/rn3 DCFWb,;=5.102E-04 rem-m3 /curie-sec.

And, D",, = A

  • X/Q
  • DCFwbgi Dvi = A'&,3,sly)
  • n
  • X/Q
  • DCFwbgi DbI = 2.679E+03 ci/assy *24 assy*0.30*2.72E-04 sec/m 3*5.102E-04 rern-m3 /curie-sec D~bti = 2.68E-03 rem I-N-4072-001

E&TS DEPARTMENT CALCULATION SHEET !PRELIM.

ECN NOJ CCN NO. N-C J E2

? O I PAGE _ OF.2 Project or ECP CaIc. No. N-4072-001 CCN CONVERSION:

I CCN NO. CCN- /

Iuu~iI loal Wnr4lin,,

rulsIlullqADUI I-,hoiM Ar-r-ie.nt IInrirA.

IIiU G "Andlinri 11101l LIUIUIQ-VI

-alli~ Ptildinn - rP L l;ICV<C; P. rl)ffeit, nnlroc IGICSU Shnnt t 97f7 nf97 O REV ORIGINAToR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 6 N.YACKLE T.REMICK I V l M.DRUCKER T T.REMICK I A8.4 Dropped Cask of Unit 1 Fuel in the Unit 2 or 3 Fuel Handling Building, Unit 2/3 EAB Beta Skin Immersion Dose Per Table A8. 1 above, Assumption A3.1 and Desirn Inputs A4.3, A4.5 and A4.6:

A(s,,+)=Assernb~y decayed inventory =2.679E+03 ci/assy n =Number of assemblies in cask =24 assy f =gap fraction = 30%I100% =0.30 X/Q =2.72E-04 sec/m 3 DCFb3 i =4.246E-02 rern-m3 /curie-sec.

And, Dbi = A * ,YQ

  • DCFbsi Db; = Al.s.mb>y) *n f
  • X/Q
  • DCFbSi Db,; = 2.679E+03 ci/assy *24 assy*0.30*2.72E-04 sec/m3*4.246E-02 remi-m/curie-sec Dbi= 2.23E-01 rein N-4 072-001

E&TS DEPARTMENT I ECN NOJ I - q)Z CALCULATION SHEET I PRELIM. CCN NO. N-8 I PAGE- OF _

Project or ECP Calc. No. N-4072-001 CCN CONVERSION:

I CCN NO. CCN -- /

Subiect Fuel Handlinq Accident Inside Fuel Handlinq Buildina - CR & Offsite Doses Sheet 268 of 270 REVI ORIGINATOR I DATE I IRE DATE REV ORIGINATOR DATE IRE DATE R 6 N. YACKLE 1 T.REMICK l l lM. DRUCKER T. REMICK II A8.5 Dropped Cask of Units 2&3 Fuel in the Unit 2 or 3 Fuel Handling Building, Unit 2/3 EAB Whole Body Garnma Immersion Dose Table A8.5-1 documents the input values and resultant whole body gamma immersion doses due to the release of Iodine-129 and Krypton-85 from the damaged Units 2&3 fuel present in the dropped cask.

As a sample calculation, the Krypton-85 %vhole body gamma immersion dose is:

Dwbz; = A(Mssmbby) *n

  • f
  • X/Q
  • DCFwbZi Db- = 4.484E+03 ci/assy *24 assy*0.30*2.72E-04 sec/m3 *5.102E-04 rem-m3 /curie-sec D~bs; = 4.5E-03 rein The total whole body gamma immersion dose at the EAB due to a dropped cask of Units 2&3 fuel in the Unit 2 or 3 FHB is 4.5E-03 rem.

TABLE A8.5-1 Isotope U23 Number of Damaged U23 to EAB Whole Body Whole Body Assembly Damaged Fuel Rod Atmospheric Gamma Gamma Activity Assemblies Gap Release Dispersion Immersion Immersion per Cask Fraction Factor DCF Dose

[Table A8.2] [Sect. A3.1J [Sect. A4.8] [Sect. A4.6] [Sect. A4.5]

(ci/assy) (assy/cask) (unitless) (sec/ml) (rem-rm 3/ci-s) (rem) 1-129 2.832E-02 24 0.12 2.72E-04 3.024E-03 6.7E-08 I Kr-85 4.484E+03 24 0.30 2.72E-04 5.102E-04 4.5E-03 I TOTAL 4.5E-03 I I

N-4072-001

E&TS DEPARTMENT CALCULATION SHEET LE Project or ECP CaIc. No. N-4072-001 Rih-df- Mipcl Handlinn 4 1 tI

_UUJt UlMADU_1 ~"KWArnnid-nt 1-11-1

-- @BWl u1 u1

-

Inside

.

Pupl Hnndlinn

. - .9 - _..@_ -U RPuildinn

-JL

- CR A Offsitp Dnopes Sqheet 9R0 nf 97n REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 6 N. YACKLE I T. REMICK v

- M. DRUCKER T. REMICK =

A8.6 Dropped C-sk of Units 2&3 Fuel in the Jnit 2 or 3 Fuel Handling Building, Unit 2/3 EAB Beta Skin Immersion Dose Table A8.6-1 documents the input values and resultant beta skin imnmrsion doses due to the release of lodine-I 29 and Krypton-85 from the damaged Units 2&3 fuel present in the dropped cask.

As a sample calculation, the Krypton-85 beta-skin immersion dose is:

Dhsi = A(assmbly)

  • n
  • f
  • x/Q
  • DCFbsi Db,; = 4.484E+03 ci/assy *24 assy*0.30*2.72E-04 sechm3 *4.246E-02 rem-nm 3/curie-sec Db,; = 3.73E-01 rem The total beta skin immersion dose at the EAB due to a dropped cask of Units 2&3 fuel in the Unit 2 or 3 FHB is 3.73E-O1 rem.

TABLE A8.6-1 Isotope U23 Number of Damaged U23 to EAB Beta Skin Beta Skin Assembly Damaged Fuel Rod Atmospheric Immersion Immersion Activity Assemblies Gap Release Dispersion DCF Dose per Cask Fraction Factor

[Table AS.21 [Sect. A3.1] [Sect. A4.8] [Sect. A4.6] [Sect. A4.5]

(ci/assy) (assy/cask) (unitless) . (sec/m 3 ) (reni-m 3/ci-s) (rem)

. -_ = . ._ _

1-129 2.832E-02 24 0.12 2.72E-04 3.71OE-04 8.23E-09 Kr-85 4.484E+03 24 0.30 2.72E-04 4.246E-02 3.73E-OI TOTAL _ - - - I - J 3.73E-0l

.1 N-4072-001

E&TS DEPARTMENT lECN NOJl LZ CALCULATION SHEET CCN NO. N-8 PRELIM.EONNOJI IPGO PAGE?.OFI~

Project or ECP CaIc. No. N-4072-001 CCN CONVERSION:

I CCN NO. CCN -- I Subject Fuel Handling Accident Inside Fuel Handling Building - CR & Offsite Doses Sheet 270 of 270 REV ORGINATOR DATE IRE I DATE REV ORIGINATOR DATE IRE I DATE R M6N.YACKLE T.REMICK lIIE

[ M.DRUCKER I T.REMICK I 4 A8.7 Dropped Cask of Units 2&3 Fuel in the Unit 2 or 3 Fuel Handling BWulding, Unit 2/3 EAB Thyroid Inhalation Dose Table A8.7-1 documents the input values and resultant thyroid inhalation dose due to the release of Iodine-129 and Krypton-85 fromth- damaged Units 2&3 fuel present in the dropped cask.

As a sample calculation, the Iodine-129 thyroid inhalation dose is:

Dahy = A(assby)

  • n
  • f
  • X/Q
  • BR
  • DCFhy Dhy = 2.832E-02 ci/assy*24 assy*0.30*2.72E-04 sec/m 3 *3.47E-04 m3 1sec*5.92E+06 rem/curie Dhy = 4.6E-02 rem The total thyroid inhalation dose at the EAB due to a dropped cask of Units 2&3 fuel in the Unit 2 or 3 FHB is 4.56E-02 rem TABLE A8.7-1 Isotope U23 Number of Damaged U23 to EAB Breathing Thyroid Thyroid I Assenibly Damaged Fuel Rod Atmospheric Rate Inhalation Inhalation I Activity Assemiblies Gap Release Dispersion DCF Dose I

[Table per Cask Fraction Factor I A8.2] [Sect. A3.1] [Sect. A4.81 [Sect. A4.6] [Sect A4.11] [Sect. A4.5] I (ci/assy) (assy/cask) (unitless) (sec/rn 3 ) (rn3/sec) (rem/ci) (rem) I 1-129 J 2.832E-02 24 0.12 2.72E-04 3.47E-04 5.92E+06 4.6E-02 I Kr-85 4.484E+03 24 0.30 2.72E-04 3.47E-04 0.00 0.00 I TOTAL l - 4.6E-02 I I

I.-

N-4072-0.01

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