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Calculation, Pool Handling Accident Dose for Vermont Yankee, Psat 3019CF.QA.05
	ML032190656
Person / Time
Site:	Vermont Yankee
Issue date:	05/30/2003
From:	Fuller E, Metcalf J; Entergy Nuclear Operations, Entergy Nuclear Vermont Yankee
To:	; Office of Nuclear Reactor Regulation
References
	BVY 03-70 PSAT 3019CF.QA.05, Rev 0
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PSAT 3019CF.QA.05 Pg2 of 13 Rev 0 Table of Contents Section Page Purpose 2 Summary of Results 2 Methodology 3 Assumptions 3 References 4 Design Inputs 4 Calculation 5 Results 7 Conclusions 13 Appendix A, Rev 0, "Check Calculation Using the STARDOSE Computer Code" 20 pages (incl 5 attachments)

Appendix B, Rev 0, 'Minimum Decay Time Giving Acceptable Control Room Dose Results without Credit for Containment" 1 page Purpose The purpose of this calculation is to provide an analysis of the Fuel Handling Accident (FHA) for Vermont Yankee. This update provides (1) implementation of the Reference I (AST) source terms and (2) both ofisite and control room doses.

Summary of Results Table I - FHA Summary ofDose Results (MEE in Remn/Applicable Reference I Limit)

Case Control Room EAB LPZ 04/ Ground-Level Release, 24-Hour Decay 0.15305/5 0.4719416.3 < 0.47194/6.3 20% Ground-Level Release, 24-Hour Decay 3.14204/5 1.59761/6.3 < 1.59761/6.3 0%h Ground-Level Release, 96-Hour Decay 0.10708/5 0.27413/6.3 < 0.27413/6.3 20% Ground-Level Release, 96-Hour Decay 2.19841/5 0.92799/6.3 < 0.92799/6.3

PSAT 3019CF.QA.05 Pg 3 of l3 Rev 0 This table shows that all cases meet the applicable limits at all locations. Appendix B explains that in order to have acceptable control room doses without any containment credit (i.e., 100P/o ground level release), a miminum of 14 days' decay is needed.

Methodology This dose analysis fully complies with NRC Regulatory Guide 1.183 (Reference 1). Following accident initiation (either at 24 or 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months after shutdown), the radionuclide inventory from the damaged fuel pins is assumed to leak out to the environment instantaneously (even though releases to the environment could be assumed to occur over a 2-hour period according to Reference 1).

Credit is taken for the plant stack in achieving an elevated release for at least a portion of the activity released from the damaged fuel. In one case, 100% of the activity is assumed to be released to the environment from the plant stack; in a second case, 20%/ of the activity is assumed to be released to the environment at ground level and 80%/o is assumed to be released to the environment from the plant stack. In no case is SGTS filtration credited. Due to these simplifying, conservative assumptions, a spreadsheet is used to calculate the control room, EAB, and LPZ doses.

The time duration that corresponds to the 20% release of activity to the environment at ground level (were a two-hour release to be considered as opposed to an instantaneous release) is different depending on release assumptions. If the activity release rate were assumed to be uniform, the 20%

release would correspond to 0.2 x 120 minutes = 24 minutes out of the two hours. If the activity release were assumed to correspond to a constant fractional release rate and 990/a of the release were assumed to occur over two hours, the 20%/o release would correspond to [ln(0.8)fln(0.0l)] x 120 minutes = 6 minutes out of the two hours. Either of these two assumptions would be consistent with Reference 1.

Releases account for:

a 1.02 multiplier on licensed power,

a radial peaking factor of 1.65,

5%gap activity (except 10%/ for Kr85 and 8% for I131),

a pin failure fraction of 0.571% corresponding to 2.1 assenblies out of 368 assemblies,

an overall iodine DF of 200 and an infinite DF for other radionuclides except for noble gas.

The TEDE values obtained from the revised analysis are compared with the 6.3 rem FHA TEDE limit for offsite doses and the 5 rem TEDE limit for the control room (Reference 1).

Assumptions Assumption 1: The accident is assumed to occur either 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months after shutdown.

Consequently, core inventories were calculated that correspond to each decay time.

Justification: Fuel handling would not begin before 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after shutdown. 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months after shutdown is more typical.

PSAT 3019CF.QA.05 Pg4 of 13 Rev 0 Assumption 2: The release to the environment from the refueling floor occurs within two hours.

Justification: Reference I Assumption 3: The DF in the refueling pool does not exceed 200 for iodine. No DF is applied to noble gas, and the DF for other radionuclides is assumed to be infinite.

Justification: Reference I Assumption 4: Credit is taken for containment collection, and elevated release of at least 80% of the activity escaping the fuel pool. No ciedit is needed (or taken) for SGTS filters.

Justification: As can be seen from the results summary, the ground level release is limited to 20%h of the activity released from the fuel pool.

References

1. "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors", US NRC Regulatory Guide 1.183, Revision 0, July 2000

2. PSAT 3019CF.QA.03, '"DESIGN DATA BASE FOR APPLICATION OF THE REVISED DBA SOURCE TERM TO VERMONT YANKEE', Revision 0

3. RADDECAY Version 3, Grove Engineering, Inc., 1990.

4. VY Calculation VYC-2260, "Bounding Core Inventories of Actinides and Fission Products for Design-Basis Applications at 1950 MWt" Revision 0

5. S. L. Humphries et al, '?RADTRAD: A Simplified Model for Radionuclide Tansport and Removal and Dose Estimation", NUREG/CR-6604, Sandia National Laboratories, December 1997.

Design Inputs Design Input Data (Reference 2 for all inputs, Item numbers given in brackets)

Power Level: 1950 MWt [8.1]

Core inventory at shutdown: see Item 1.1 of Reference 2 Total number of fuel assemblies in core: 368 assemblies [1.2]

Number of damaged assemblies: 2.1 [2.41 Gap release factions:

Radio-nmclide Release Grop Fraction from Gap to Coolant Kr-85 10%

Other NG 5%

1-131 8%

Oter lodines 5% [2.5]

PSAT 3019CF.QA.05 Pg 5 of 13 Rev 0 Peaking factor. 1.65 [2.6]

Control Room Free Volume: 41,533.75 f 3 [3.4]

X/Q values in sec/M3:

EAB: 1.7E-3 (ground-level) 2.03E-4 (1lhalf-hour elevated), 1.54E-3 (2nd half-hour elevated), 9.17E-5 (remainder elevated) [5.1]

LPZ:

CR: 5.89E-3 (ground-level) 2.39E-4 (1 half-hour elevated), 1.05E-6 (2 nd half-hour elevated), 8.7E-7 (remainder elevated) [53]

LPZ dose not necessary since release is limited to two hours and EAB is more limiting Breathing Rate in n/s (fiom start of release): 3.5E-4 (5.4]

Iodine Species: 99.85% elemental, 0.15% organic* [2.7]

- Iodine chemical form not critical since control room filters are not used. Elemental iodine DF adjusted to obtain overall iodine of DF of 200 per Reference 1. No DF applied to organic iodine.

Calculation Core inventories at one or four days after shutdown are calculated using the RADDECAY Code (Reference 3). The gap activityofnoble gas andiodine (set at99.85% elemental, 0.15% organic per References 1 and 2) is added fiom the core tothe gap.

The starting point of the calculation was the t = 0 shutdown inventories (CiIMWt) from Reference 2, Item 1.1. RADDECAY was then run starting with the t = 0 inventories for the noble gas and iodine isotopes. Given the activity (Ci or Ci'MWt) of an isotope at t = 0, RADDECAY calculates the curies or Ci/MWt at any subsequent time of that isotope and its daughters. To get the total curies of the isotope of interest one must add the curies resulting from its direct decay plus the curies resulting from decay in chains in which it is a daughter product.

For Kr83m, Kr85, Kr85m, 1133 and 1134, there were no shutdown activities listed for certain of

'their parent nuclides (Br83, Br85, Tel33, Tel33m, and Te134). These were obtained directly from Reference 4. In all cases, the activity contribution from these additional nuclides is negligible except for Br83 to Kr83m and Tel34 to I134. While the parents contributed markedly to the activity for Kr83m and I134, the EAB and CR dose contribution for both of these nuclides is zero to five significant figures; therefore, the contributions have no significance for the dose.

The final activities are shown in Table 2.

PSAT 3019CF.QA.05 Pg 6 of 13 Rev 0 Table 2 - Core Inventories (per MWt) for FHA Nuclide Shutdown Adjusted 24 Hours 96 Hours Br83 4.24E+03 Kr83m 4.24E+03 same 15.6 negligible Br85 9.61E+03 Kr85m 9.71E+03 same 239 negligible Kr85 5.05E+02 1.OIE+03 1010 1009 ICr87 1.94E+04 same 0.038 negligible Kr88 2.75E+04 same 72.3 negligible Er89 3A6E+04 s negligible negligible Tel31m 4.31E+03 1131 2.85E+04 4.56E+04 42105 32776 Xe131m 3.18E+02 same 327 338 Tel32 3.97E+04 1132 4.05E+04 same 33065 17466 Tcl33m 2.30E+04 *

Tel33 3.39E+04 1133 5.79E+04 same 26656 2420 Xel33m 1.76E+03 sanE 1594 766 Xel33 5.78E+04 same 55528 40184 Te134 5.3lE+04 1134 6A3E+04 same negligible negligible 1135 5.39E+04 same 4351 2.3 Xel35m 1.14E404 same negligible negligible Xel35 2.33E+04 same 15285 106 Xe137 5.07E+04 same negligible negligible Xel38 5.05E+04 same negligible negligible

Considered as parent only These activities are compared to those calculated as part of the check calculation in Appendix A (see Table A-1).

The offsite X/Qs are from Reference 2 as previously noted. A weighted-average X/Q is calculated depending on the percentage of activity released with the elevated release CR and EAB XIQ and the ground-level release CR and EAB XIQ. Cases for both zero and 20% ground release are considered. As noted under Methodology, if it is assumed that the normalized release to the environment is linear (i.e., 0.5 per hour for two hours), then the 20% ground-level X/Q means thaithe pground-level release lastedOA hours or 24 minutes. If a constant fracional release rate is assumed such that 99% is released in two hours (23 per hour), then the 20%/o ground-level X/Q means that the ground level release lasted approximately 0.1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or 6 minutes.

So using the database (Reference 2) values as follows for the CR:

Stack (fimig): 2.39E-4 Stack (norm): 1.05E-6 (1/2 hour), 8.7E-7 (I hour)

RB siding: 5.89E-3

PSAT 3019CF.QA.05 Pg 7 of 13 Rev O the "zero" case would just.use a weighted average 0.25 x 2.39E-4 + 0.25 x I.05E-6 + 0.5 x 8.7E-7 = 6.04E-5, while the "20%" case would use a weighted average of 0.2 x 5.89E-3 + 0.25 x 2.39E-4 + 0.25 x 1.05E-6 + 0.3 x 8.7E-7 = 1.24E-3.

In like manner, for the EAB dose:

Stack (fumig): 2.03E-4 Stack (norm): 1.54E-4 (1/2 hour), 9.17E-5 (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months )

Ground-level: 1.7E-3 the-wzero"asewould just use a weighted average 0.25 x 2.03E-4 + 0.25 x 1.54E-4-+0.5-x 9.17E-5 = 1.35E4, while the t200/o' case would use a weighted average of 0.2 x 1.7E-3 + 0.25 x 2.03E-4 + 0.25 x 1.54E-4 + 0.3 x 9.17E-5 = 4.57E4.

The breathing rate of 3.5E-4 m3 /s is taken from Reference 2.

Note that no credit is taken for the SGTS filtration.

Results An EXCEL spreadsheet calculation has been earned out to obtan the results for each of four cases (0% and 20% elevated release for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months decay). The spreadsheet is constructed as follows:

Rows l and 2: Title and headings forX/Q values (EAB and CR)

Row 3: Reactor Power (MWt) accounting for uncertainties Row 4: Control Room free volume (t 3 )

Row 5: Release fraction (fraction of total inventory released during the accident)

RF = 0.05 x (no. of damaged assemblies/total no. of fuel assemblies in core)

RF = 0.05 x 2.1 /368 = 2.85E-4 Row 6: Radial power peaking factor Column 1: Radionuclides, with distinction between iodine chemical forms Column 2: Decayed core inventory (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months , as appropriate)

Column 3: Whole Body DCF, equal to "Cloudshine Effective" from Ref 5 after conversion to 4: reM_-M3 /Ci-sc. -. *-- .. ..

Column4: CEDE DCF, equal to "Inhaled Chronic Effective" from Ref. 5 after conversion to rem/Ci Column 5: TEDE DCF = (Whole Body DCF) + (CEDE DCF x Breathing Rate)

Column 6: CR TEDE DCF = (Whole Body DCF x (CR Volume) 0 3/l 173) + (CEDE DCF x Breathing Rate)

This CR DCF differs fiom the TEDE DCF as it includes a finite volume correction for the Whole Body dose taken from Ref 1. CR volume must be in ft3.

PSAT 3019CF.QA.05 Pg 8 of 13 Rev 0 Column 7: EAB TEDE = (Ci/MWt) x (Power Level) x (Release Fraction) x (Peaking Factor) k (Appropriate Nuclide Multiplier of 1.0 for noble gas, 0.0015 for organic iodine, or 0.9985 divided by DF = 285 for elemental iodine) x (EAB X/Q) x (TEDE DCFT)

Column 8: CR TEDE = (CiIMWt) x (Power Level) x (Release Fraction) x (Peaking Factor) x (Appropriate Nuclide Multiplier of 1.0 for noble gas, 0.0015 for organic iodine, or 0.9985 divided by DF = 285 for elemental iodine) x (CR X/Q) x (CR TEDE DCF)

The "appropriate nuclide multipilers" are 1.0 for the noble gases, 0.0015 for organic iodine, and (1.0 - 0.0015y(refueling pool DF) for the elemental iodine. The refueling pool DF for elemenatal iodine is calculated as follows:

1. Assume an effective DF of 200.

2. The fraction of the iodine inventory released from the pool is 1/200 0.005. Of this, 0.0015 is for organics, so the elemental iodine release fiaction is 0.0035.

3. DF = 1.0/0.0035 z285.

The spreadsheet results for 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months decay before the fuel handling accident are shown in Tables 3 and 4 for 0%/o ground level release and 20%h ground level release, respectively. Corresponding results for 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months after shutdown appear in Tables 5 and 6. Contrrol room and EAB doses are explicitly calculated, and because the release occurs within two hours, the EAB doses are bounding for the LPZ.

PSAT 3019CF.QA.05 Pg 9 of 13 Rev 0 Table 3. Doses after a Fuel Handling Accident (0% ground-level release, 24-hour decay):

VY FHA (24 hrs) EAB CR XIQs 1.35E-04 6.04E-05 sec/m3 (0°/e release at ground level)

Power= 1950 MWt CR Vol = 41533.75 ft3 Rel Frac. = 2.85E-04 Pealing= 1.65 WB CEDE TEDE CR TEDE EAB CR Nuclide Ci/MW DCF DCF DCF DCF TEDE TEDE Kr83m. -.1,56B+01 1.49E-05 .0 .1.5E-95. 5E-07 9Q.O00 0.00000 Kr85m 2.39E+02 0.0277 0 0.0277 0.0009 0.00082 0.00001 Kr85 1.01E+03 4.40E-04 0 0.00044 lE-05 0.00006 0.00000 Kr87 3.80E-02 0.1524 0 0.1524 0.0047 0.00000 0.00000 Kr88 7.23E+01 0.3774 0 0.3774 0.0117 0.00338 0.00005 Kr89 0.OOE+00 0.323 0 0.323 0.01 0.00000 0.00000 Xel3lm 0.OOE+00 0.00149 0 0.00149 5SE-05 0.00000 0.00000 Xel33m 0.OOE+00 0.00507 0 0.00507 0.0002 0.00000 0.00000 Xel33 5.30E+04 0.00577 0 0.00577 0.0002 0.03787 0.00053 Xel35m 0.OOE+00 0.07548 0 0.07548 0.0023 0.00000 0.00000 Xel35 1.45E+04 0.04403 0 0.04403 0.0014 0.07903 0.00110 XeI37 0.OOE+00 0.0303 0 0.0303 0.0009 0.00000 0.00000 Xel38 O.OOE+00 0.199 0 0.199 0.0062 0.00000 0.00000 11310rg 4.21E+04 0.06734 32893 11.5799 11.515 0.09054 0.04028 11320rg 3.31E+04 0.4144 381.1 0.54779 0.1462 0.00336 0.00040 11330rg 2.67E+04 0.10878 5846 2.15488 2.0495 0.01067 0.00454 11340rg 0.OOE+00 0.481 131.35 0.52697 0.0609 0.00000 0.00000 11350rg 4.35E+03 0.3069 1228.4 0.73684 0.4395 0.00060 0.00016 I131EIem 4.21E+04 0.06734 32893 11.5799 11.515 0.21147 0.09408 I132Elem 3.31E+04 OA144. 381.1 0.54779 0.1462 0.00786 0.00094 I133Elem 2.67E+04 0.10878 5846 2.15488 2.0495 0.02491 0.01060 I134Elem O.OOE+00 0.481 131.35 0.52697 0.0609 0.00000 0.00000 1135Elem 4.35E+03 0.3069 1228A 0.73684 0.4395 0.00139 0.00037 Total TEDE= 0.47194 0.15305

PSAT 3019CF.QA.05 Pg lOofl3 Rev 0 Table 4. Doses after a Fuel Handling Accident (20% ground level release, 24-hour decay):

VY FHA (24 hrs) EAB CR Ground Level XJQs = 4.57E-04 1.24E-03 sec/m3 (20% release at ground level)

Power= 1950 MW(t)

CR Vol = 41533.75 f3 Rel Fract = 2.85E-04 Pealing = 1.65 WB CEDE TEDE CR TEDE EAB CR Nuclide Ci/MW DCF DCF DCF DCF TEDE TEDE Z r~ 1.56E+01 1.49E-05 - ° .I.SE-05 ._Ei97 -QtQOM 0...0,00 Kr85m 2.39E+02 0.0277 0 0.0277 0.0009 0.00277 0.00023 Kr85 1.O1E+03 4.40E-04 0 0.00044 IE-05 0.00019 0.00002 Kr87 3.80E-02 0.1524 0 0.1524 0.0047 0.00000 0.00000 Kr88 7.23E+01 0.3774 0 0.3774 0.0117 0.01143 0.00096 Kr89 O.OOE+00 0.323 0 0.323 0.01 0.00000 0.00000 Xel3lm O.OOE+OO 0.00149 0 0.00149 SE-05 0.00000 0.00000 Xei33m 0.OO+o00 0.00507 0 0.00507 0.0002 0.00000 0.00000 Xel33 5.30E+04 0.00577 0 0.00577 0.0002 0.12820 0.01079 Xel35m O.OOE+OO 0.07548 0 0.07548 0.0023 0.00000 0.00000 Xel35 1.45E+04 0.04403 0 0.04403 0.0014 0.26754 0.02252 Xe137 O.OOE+00 0.0303 0 0.0303 0.0009 0.00000 0.00000 Xel38 0.OOE+00 *0.199 0 0.199 0.0062 0.00000 0.00000 I13lOrg 4.21E+04 0.06734 32893 11.5799 11.515 0.30648 0.82691 11320rg 3.31E+04 0.4144 381.1 0.54779 0.1462 0.01139 0.00825 11330rg 2.67E+04 0.10878 5846 2.15488 2.0495 0.03611 0.09318 11340rg 0.00E+00 OA81 131.35 0.52697 0.0609 0.00000 0.00000 11350rg 4.35E+03 0.3069 1228A 0.73684 0.4395 0.00202 0.00326 I131Elem 4.21E+04 0.06734 32893 11.5799 11.515 0.71585 1.93140 I132Elem 3.31E+04 0.4144 381.1 0.54779 0.1462 0.02659 0.01926 I133EIem 2.67E+04 0.10878 5846 2.15488 2.0495 0.08433 0.21763 I134Elem 0.OOE+OO 0.481 131.35 0.52697 0.0609 0.00000 0.00000 I135Elem 4.35E+03 0.3069 1228.4 0.73684 0.4395 0.00471 0.00762 Total TEDE 1.59761 3.14204

PSAT 3019CF.QA.05 Pg 11 of 13 Rev 0 Table 5. Doses after a-Fuel Handling Accident (0% ground level release, 96-hour decay). -

VY FHA (96 hrs) EAB CR Ground Level XlQs = 1.35E-04 6.04E-05 sec/m 3 (0%/o release at ground level)

Power= 1950 MWt CR Vol = 41533.8 ft3 Rel Frac. = 2.85E-04 Peaking = 1.65 WB CEDE TEDE CR TEDE EAB CR Nuclide Ci/MW DCF DCF DCF DCF TEDE TEDE Kr83m -1.49E-05 .;0- ; .1,51Q5 *. - 7- 400000.0000.

Kr85m 0 0.0277 0 0.0277 0.0009 0.00000 0.00000 Kr85 1009 4.40E-04 0 0.00044 E-S05 0.00005 o.o00 Kr87 0 0.1524 0 0.1524 0.0047 0.00000 0.00000 Kr88 0 0.3774 0 0.3774 0.0117 0.00000 0.00000 Kr89 0 0.323 0 0.323 0.01 0.00000 0.00000 Xel31m 338 0.00149 0 0.00149 SE-05 0.00006 0.00000 Xel33m 766 0.00507 0 0.00507 0.0002 0.00048 0.00001 Xel33 40184 0.00577 0 0.00577 0.0002 0.02871 0.00040 Xel35m 0 0.07548 0 0.07548 0.0023 0.00000 0.00000 Xe135 106 0.04403 0 0.04403 0.0014 0.00058 0.00001 Xe137 0 0.0303 0 0.0303 0.0009 0.00000 0.00000 Xel38 0- 0.199 0 0.199 0.0062 0.00000 0.00000 11310rg 32776 0.06734 32893 11.5799 11.515 0.07048 0.03135 11320rg 17466 OA144 381.1 0.54779 0.1462 0.00178 0.00021 11330rg 2420 0.10878 5846 2.15488 2.0495 0.00097 0.00041 11340rg 0 0.481 13 1.35 0.52697 0.0609 0.00000 0.00000 11350rg 2.3 0.3069 1228.4 0.73684 0.4395 0.00000 0.00000 I131Elem 32776 0.06734 32893 11.5799 11.515 0.16461 0.07323 I132Elem 17466 0.4144 381.1 0.54779 0.1462 0.00415 0.00050 I133Elern 2420 0.10878 584 2.15488 2.0495 0.00226 0.00096 I134Elemn 0 0.481 131.35 0.52697 0.0609 0.00000 0.00000 I135Elern 2.3 0.3069 1228.4 0.73684 0.4395 0.000(0 0.00000 Total TEDE= 0.27413 0.10708

PSAT 3019CF.QA.05 Pg 12 of 13 Rev 0 Table 6. Doses after a Fuel Handling Accident (20% ground level release, 96-hour decay):

VY FHA (96 hrs) EAB CR Ground Level X/Qs = 4.57E-04 1.24E03 sechn3 (20%/o release at ground level)

Power = 1950 MW(t)

CR Vol = 41533.8 ft3 Rel Fract - 2.85E-04 Peaking = 1.65 WB CEDE TEDE CR EAB CR Nuclide Ci/MW DCF DCF DCF DCF TEDE TEDE KEr83m* - 49E&05 - 1.5EB 1)- -E-07-- 0.00000 A"Q00000;.

Kx85m 0 0.0277 0 0.0277 0.0009 0.00000 0.00000 Kr85 1009 4.40E-04 0 0.00044 IE-05 0.00019 0.00002 Kr87 0 0.1524 0 0.1524 0.0047 0.00000 0.00000 Kr88 0 0.3774 0 0.3774 0.0117 0.00000 0.00000 Kr89 0 0.323 0 0.323 0.01 0.00000 0.00000 Xel3im 338 0.00149 0 0.00149 SE-OS 0.00021 0.00002 Xel33m 766 0.00507 0 0.00507 0.0002 0.00163 0.00014 Xel33 40184 0.00577 0 0.00577 0.0002 0.09720 0.00818 Xel35m 0 0.07548 0 0.07548 0.0023 0.00000 0.00000 Xel.35 106 0.04403 0 0.04403 0.0014 0.00196 0.00016 Xel37 0 0.0303 0 0.0303 0.0009 0.00000 0.00000 Xe138 - 0.199 0 0Q199 0.0062 0.00000 0.00000 11310rg 32776 0.06734 32893 11.5799 11.515 0.23858 0.64369 11320rg 17466 0.4144 381.1 0.54779 0.1462 0.00601 0.00436 11330rg 2420 0.10878 5846 2.15488 2.0495 0.00328 0.00846 11340rg 0 0.481 131.35 0.52697 0.0609 0.00000 0.00000 11350rg 2.3 0.3069 1228.4 0.73684 0.4395 0.00000 0.00000 I131Elem 32776 0.06734 32893 11.5799 11.515 0.55723 1.50345 I132Elem 17466 OA144 381.1 0.54779 0.1462 0.01405 0.01018 I133Elem 2420 0.10878 5846 2.15488 2.0495 0.00766 0.01976 I134EIem 0 0.481 131.35 0.52697 0.0609 0.00000 0.00000 1135Elem 2.3 0.3069 1228.4 0.73684 0.4395 0.00000 0.00000 Total TEDE = 0.92799 2.19841

PSAT 3019CF.QA.05 Pg 13 of 13 Rev 0 Reference I states that the control room dose limit is 5 rem TEDE and that the offsite dose limit for the FRA is 6.3 rem TEDE. The results from Tables 3 through 6 can be compared to these limits.

Note that there is considerable margin for the control room doses and for the EAB and LPZ doses.

Conclusions The FHA control room and offsite doses are well within their Reference I limits if the ground level release is limited. Even if 20% of the release is at ground level, the Emits are not exceeded, with either 24 or 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months of decay prior to the start of the accident

PSAT 3019CF.QA.05 Page Al of 5 Rev 0 Appendix A - Check Calculation Using the STARDOSE Computer Code This appendix provides a check calculation for the FHA analysis for VY using the STARDOSE computer code (Reference A-1). The analysis makes use of the same dose conversion factors (DCFs) as used in the dose calculation spreadsheets provided in the main body of the calculation.

The release is assumed to occur on the refueling floor, and the activity release to the environment is designed to be complete within two hours. For cases involving ground-level release, the assumption is made that a fractional release rate necessary to release 99% of the acitivity to the environment in two hours (i.e4LOp.0384 peFrinute)occuzsfor six minutes at the start of the accident. Beyond that time (i.e., for the next 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months , for the next 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months after that, and finally for the last 0.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months ), the elevated release X/Qs are used in decending order of magnitude for both the EAB dose and the CR dose. Fractional release rates are then varied to obtain a average absolute release rate of 0.5 per hour for the next hour (i.e., 0.0125 per minute for the first half of that one hour and then 0.02 per minute for the last half of that one hour) and finally to release the remaining 30%/ of the activity withing the last 0.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months (0.063 per minute). By so doing, 20% of the activity is released within the first six minutes (ground-level release), 25%

within the next half-hour, another 25% within the half-hour after that, and then finally, 29%/o during the remaining 0.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months (leaving 1%not released). This is a conservative interpretation of the Reference A-2 requirement that the release be complete within two hours, and it is consistent with the X/Q averaging done in the main body of the calculation.

For cases not involving ground-level release, the intent is to release 25% within the first half-hour, 25% within the next half-hour, and 49% within the final one hour (leaving 1% not released). The corresponding fractional release rates are 0.0096 per minute, 0.01335 per minute, and 0.065 per minute, respectively.

The control room dose calculation is continued for a minimum of 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months after the end of the release. With a fresh air intake rate of 3700 cfn and a control room volume of 4.15E4 ft3 (Reference A-3), the room turnover rate is 0.09 per minute which means nearly 120 volume changes in 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months . Continuing the dose calculation for 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months the end of the release ensures that the control room dose is fully accumulated.

STARDOSE Calculation The model in STARDOSE consists of three control volumes. The first control volume is the gap (nominally I00 ft3), the second is the reactor building (RB) refueling floor (also nominally 100 ft3), and the third is the control room (4.15E4 f 3 per Reference A-3). Note that the nominal 100 ft3 volumes are used to conveniently calculate exchange rates.

The core power is assumed to be 1950 MWt as in the main body of the calculation. The gap activity of noble gas, iodine (set at 100% organic because the iodine form is not relevant without filters in the control room), and tellurium (as an iodine precursor) is added from the core to the gap over the first 0.01 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of the analysis. It is added at 8.25 core inventories per hour so that the release is 8.25%. This 8.25% is to account for a "base" gap fraction of 5% (Reference A-2)

PSAT 3019CF.QA.05 PageA2 of 5 Rev 0 and a peaking factor of 1.65 (Reference A-3). Note, however, that because the gap activities for Kr-85 and 1-131 are respectively 10%/o and 8%per Reference A-2, the inventories of these two radionuclides in the attached STARDOSE LIBFELE1.TXT file were increased by a factor of 2 and 8/5, respectively, as compared to the activities given in Reference A-3.

Once the activity has been established in the gap, it is allowed to decay until 23.9833 or 95.9833 hours0.114 days 2.731 hours 0.0163 weeks 0.00374 months , as appropriate. It is then released to the RB at 0.571 cfm (0.571% per minute) for 0.0167 hours0.00193 days 0.0464 hours 2.761243e-4 weeks 6.35435e-5 months (one minute) so that the assumed 0.571% of the assemblies are represented as in the main body of the calculation. A filter efficiency of 0.995 is used to account for the water DF of 200

. . . *.appliedl.tolt ine..Since telluriumrwas also.released to provide additional iodine during the..

decay period, a filter efficiency of 0.99999 is used to prevent its subsequent release to the RB (although a small amount would be present). No other particulates are assumed to be released in the STARDOSE model because (per Reference A-2), the scrubbing DF is assumed to be infinite for that activity.

All of this activity is in the RB by24 hours or 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months , as appropriate. At 24196 hours, the release to the environment is assumed to begin at the rates specifed above. Note that no credit for SGTS filtration is taken.

The XIQs are from Reference A-3 but displaced by 24 or 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months , as appropriate. The breathing rate of 3.5E-4 m3/sec is also taken from Reference A-3.

As for the control room, a fresh air intake rate of 3700 cfmn (Reference A-3) and an occupancy factor of unity are used.

Four cases are run (as in the main body of the calculation): 00/h and 20% ground-level release and 24- and 96-hour decay times.

The L.lBLEI.TXT file of Attachment A-I, common to all AST STARDOSE runs, contains the radionuclide input data. The core inventories listed in Column 5 are from Reference A-3 (with the Kr-85 and 1-131 inventories increased by a factor of 2 and 8/5, as described above). The Dose Conversion Factors (Column 8 for whole body and Column 12 for CEDE) are the same as in the main body of the calculation. Decay constants (per second) come firom Reference A-4.

Input files are provided as Attachments A-2 through A-5.

Output file excerpts are provided in the Results section below. The core inventory in the gap at the start ofthe gap release is shown in the following table for comparison to the values in the main body of the calculation. Note that the agreement is good except for Kr83m and, to a lesser extent, for Xel3lr and Xel33m. This is because the daughter ingrowth formulation in STARDOSE is less sophisticated than for the RADDECAY code used in the main body of the calculation.

However, the important daughter ingrowth contributions are properly represented in STARDOSE, and the three dose contributors just mentioned have very little impact on the overall dose calculation.

PSAT 301 9CF.QA.05 Page A3 of 5 Rev 0 Table A-I Gap Inventory Comparison (Ci/IMWt at Stated Time, No Pealdng, Multipliers for Kr85 and 1131 Included)

Nuclide 24 Hours* 24 Hours** 96 Hours* 96 Hours**

Kr83m 15.6 I negligible 0 Kr18m 239 219 negligible 0 Kr85 1010 1007 1009 1007 Kr87 0.038 0.04 negligible 0 KrM8 72.3 72 negligible 0

-. Kr89 ~- eglwgb'e -7

-- - negligible -..

1131 42105 42207 32776 32883 Xel31m 327 300 338 252 1132 33065 32945 17466 17218 1133 26656 26107 2420 2393 Xel33m 1594 1299 766 527 Xel33 55528 55571 40184 40466 I134 negligible O negligible 0 1135 4351 4563 2.3 3 Xel3Sm negligible 0 negligible 0 Xel35 15285 15540 106 116 Xe137 negligible 0 negligible 0 Xel38 negligible 0 negligible 0

Main body of calculation

- STARDOSE Results Excerpt Rom STARDOSE output correonding to Attachment 2 INPUT.DAT (0%/o ground-level release. 24-hour decay):

ControlRoom thyroid wbody skin CEDE Total dose: 4.90E+000 1. 92E-003 8.89E-002 1.51E-001 Noble gas 0.00E+000 1.75E-003 8.69E-002 o. OOE+000 Org iodine 4.90E+000 1.63E-004 1.98E-003 1. S1E -001 environment thyroid wbody skin CEDE EAB dose: 1.05E+001 1.31E-001 1.89E-001 3.24E-001 thyrdeab wbodyjeab skin eab CEDE eab Noble gas 0. 00E+000 1.20E-001 1.85-001 0.001+000 Org iodine I. 05E+001 1.08E-002 4.09E-003 3.24E-001

PSAT 3019CF.QA.05 Page A4 of 5 Rev 0 Excerpt from STARDOSE output corresoonding to Attachment 3 INPUT.DAT (20% ground-level release. 24-hour decaA):

ControlRoom thyroid wbody skin CEDE Total dose: 1.03E+002 4.OBE-002 1.69E+O0o 3. 18E+o00 Noble gas 0.OOE+000 3.73E-002 1.84E+000 O.OOE+000 Org iodine 1.03E+002 3.57E-003 4.27E-002 3.18E+000 environment

"-B se:

do4' ' '-

"" 70E+0O1 4.73E-00l Xk-00hl; 6-.77Eay - - E+0 4 00 ' ' -- - ^ ;

EAB dose: 3.70E+001 4.73E-001 6.77B-001 1.14E+000 thyrd eab wbody eab skin eab CEDE eab Noble gas O.OOE+000 4.31E-001 6.61E-001 0.OOE+000 Org iodine 3.70E+001 4.15E-002 1.54E-002 1.14E+000 Excernt fiom STARDOSE outnut conremondiny to Attachment 4 INPUTDAT 0r%emund-level release. 96-hour decay:

ControlRoom thyroid wbody skin CEDE Total dose: 3.50E+000 4.91E-004 2.75E-002 1.07E-001 Noble gas 0.OOE+000 4.16E-004 2.67E-002 0.OOE+000 Org iodine 3.50E+000 7.52E-005 7.94E-004 1.07E-001 environment thyroid wbody skin CEDE EAB dose: 7.52E+000 3.38E-002 5.91E-002 2.30E-001 thyrdeab wbody eab skin eab CEDE eab Noble gas 0. OOE+000 2.88E-002 5.75E-002 0.OOE+000 Org iodine 7.52EB000 4. 94E-003 1.63E-003 2.30E-001 Excerpt from STARDOSE output correspondintto Attachment 5INPUT2DAT (20% ground-level release, 96-hour decay):

Control-Room thyroid wbody skin CEDE Total dose: 7.36E+001 1.04E-002 5. SE-001 2.25E+000 Noble gas 0.OOE+000 8.75E-003 5.63E-001 0.OOE+000 Org iodine 7.36E+001 1.64E-003 1.73E-002 2.25E+000 environment thyroid wbody skin CEDE EAB dose: 2.64E+001 1.20E-001 2.08E-001 8.OSE-001 thyrd eab wbodyeab skin eab CEDE eab Noble gas O.OOE+000 1.OlE-001 2.02E-001 0.OOE+000 Org iodine 2.64E+001 1. 92E-002 6.22E-003 8.05E-001

PSAT 3019CF.QA.05 Page A5 of 5 Rev 0 Table A-2 summarizes offsite and control room dose results for all four cases:

Table A Doses for the FHA Analysis (in rem)

Conclusions The dose agreement for all cases is excellent. The STARDOSE runs confinn the results from the main body of the calculation.

Reference A-2 states that the control room dose limit is 5 rem TEDE and that the offsite dose limit for the FHA is 6.3 rem TEDE. The results from Table A-2 can be compared to these limits.

For the limiting case of only 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 's decay and 20% ground-level release, the F.HA control room dose represents about 63% of the 5-rem limit. The EAB dose has almost a factor four margin.

References A-1. "STARDOSE Model Report", Polestar Applied Technology, Inc., PSATCI09.03, January 1997 A-2. "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors", US NRC Regulatory Guide 1.183, Revision 0, July 2000 A-3. PSAT 3019CF.QA.03, "Design Data Base forApplication of the Revised DBA Source Term to Vermont Yankee", Revision 0 A-4. NUREG/CR-5106 (Manual for TACT5 - Version SAIC 9/23187), File MLWRICRP.30

PSA. .019CF.QA.05 Attai.sent A LIBFILEI.TXT Rev 0 n-isotopes 20 n_isotopegroups 11 ci, Kr83m N Gas NONE NONE 4.242+03 1.042-04 0 1.49E-05 0 0 0 0 10 0 0 0 0 KrSSm N Gas NONE NONE 9.71E+03 4.39E-OS 0 0.0277 0 0 0.05 0: 0.22 0 0 o 0 0 KrB5 NGan NONE NONE 1.01E+03 2.04B-09 0 4.402-04 0 0 0.05 0. 0.22 10 0 o o 0 Kr87 N Gas NONE NONE 1.94El04 1.52B-04 0 0.1524 0 0 0.34 0 1.48 10 0 0 0 0 Kr88 N Gan NONE NONE 2.75B+04 6.882-05 0 0.3774 0 0 0.08 02 0.35 10 0 o 0 0 Kr89 N Gan NONE NONE 3.46E+04 3.63E-03 0 0.323 0 0 0.35 0 1.52 0 D 0 0 0 Xel3lm N Gas NONE NONE 3.18E+02 6.682-07 0 0.00149 0 0 Q.02 0 10.04 0 o 0 0 0 'I Xel33m N Gas NONE NONE 1.76E203 3.492-06 0 0.00507 0 0 0>.03

.0, 0 10.13 0 0 0 o -o Xel33 N Gas I1330i rg ,INONE 5.78E+04 1.52E-06 0 0.00577 0 0 0;.01 0 10.04 0 o o 0 .

Xel35m N Gan NONE !NONE 1.14E+04 7.40E-04 0 0.07548 0 0 X.02 0 0.09 0 0 0 O 0 Xel35 N Gan I135O1rg MNONE 2.332+04 2.09E-05 0 0.04403 0 0 0.06 0 0.26 0 0 0 o '0 Xel37 N Gan NONE NONE 5.07E+04 2.96B-03 0 0.0303 0 0 0.46 2 0 0 0 o 0 Xel38 N Gas NONE NONE 5.SE+04 6.80E-04 0 0.199 0 0 0.15 0 .65 0 0 0 o 0 I1310rg OrgI Tel31m NONE 4.57B+04 9.'96E--07 1080400 0.06734 0 0.0D3 32893 0.13 0 0 0 0 0 11320rg Org I Te132 NONE 4.05E+04 8.27B-05 6438 0.4144 0 0 g,.1 381.1 0.48 0 0 0 0 ,0 I1330rg OrgI NONE Xel33 5.79B+04 9.228-06 179820 0.10878 0 0.09 5846 0.39 o 0 0 0 0 11340rg OrgI NONE INONE 6.43B+04 2.23E-04 1065.6 0.481 0 0 0.14 131.35 0.61 0 0 0 0 0 I1350rg Org.I NONE Xel35 5.39B+04 2.86E-05 31302 0.3069 0 0 d.o08 1228.4 0.35 0 0 0 0 0 Tel3lm TeGrp NONE 11310rg 4.31E+03 6.422- -06 0 0 0 0 0 0 0 0 0 0 0 0 Tel32 TeGrp NONE I1320rg 3.972+04 2.51E-06 0 0 0 0 0 0 0 0 0 0 0 i

Ti) 7 1

i I:

I

PSAT 3019CF.QA.05 Attachment A INPUTDAT, 24 hr, 0%/0 Rev 0 edit time 0.0 0.01 23.9833 24.0 48.0 end edittime participatingisotopes Kr83m Kr85m Kr8s Xr87 Kr88 Kr89 Xel31m Xel33m Xe133 Xel35m Xel35 Xe137 Xel38 I1310rg 11320rg 11330rg I1340rg I1350rg Tel3lm Tel32 end participating isotol core thermalpower 1950 elemental:'i'bdie- -frac 5 ' 0 organic iodine frac 1.0 particulateiodine frac 0.0 release frac to controlvolume GAP Time N Gas I Grp CsGrp TeGrp BaGrp NItls CeGrp LaGrp SrGrp 0.01 8.25 8.25 0 8.25 0 0 0 0 0 48 0 0 0 0 0 0 0 0 0 endto control volume end_release frac end core controlvolume objitype OBJ _CV name GAP air volume 100 water volume 0 surfacearea ... -a has recirc filter f alse end control volume controlvolume obitype OBJ CV name RB airvolume 100 water_ volume 0 surface area 0 has recirc filter false endcontrol volume control volume obj. type OBJ CR name Control_Room air volume 4.15e+004 water volume . .... . ..-

surfacearea 0 has recirc filter false breathing yate Time (hr) Value (cms) 48 0.00035 end breathingrate occupancy factor Time (hr) Value (frac) 48 1 end occupancy factor endcontrol volume junction

PSAT 3019CF.QA.05 Attacbment A NPIUT.DAT, 24 hr, 0%/6 Rev 0 junction type AIR JUNCTION downstream location AIRSPACE upstream CORE downstream GAP has filter false flow rate Time (hr) Value (cfm) 48 1 end flow rate endjunction junction junction type AIR JUNCTION do istiea 'Iocatioh- - AIR SPACE;;

upstream GAP downstream RE has filter true flow rate Time (hr) Value (cfm) 23.9833 0 24 0.571 48 0 endflowrate filter efficiency Time NobleGas Elemlodine OrgIodine PartIodine Solubles Insolubles 48 0 0 0.995 o 0 0.99999 end filter-efficiency frac 4 daughter resusp Time NobleGas ElemIodine orgIodine PartIodine Solubles Insolubles 48 0 0 0 0 0 0 end frac_4_daughter resusp reevolution rate Time NobleGas ElemIodine OrgIodine PartIodine Solubles Insolubles 48 0 0 0 0 - 0 0 endreevolutionrate endjunction junction junction type AIR JUNCTION downstream location AIRSPACE upstream RB downstream Eenvironment hasfilter !aloe flow rate Time (hr) Value (cfm) 24 0 24.5 0.96 25 1.335. -.

26 6.5 48 0 end flowrate X_over_Q_4_site boundary Time (hr) Value (s/m*3) 24 0 24.5 2.03e-4 25 l.54e-4 26 9.17e-5 48 0.0 end X_over_Q_4_siteboundary Xover_Q_4low_population zone Time (hr) Value (s/l*3)

PSAT 3019CF.QA.05 Attachment A INPULDAT, 24 hr, 0%

Rev 0 48 0.0 end_X_over_Q_4_low_populationzone Xover_Q_4 ctrl room Time (hr) Value (s/m*3) 24 0.0 24.5 2.39e-4 25 1.05e-6 26 8.70e-7 48 0.0 end X overQ_4_ctrl room endj unction junction r ~~junetiorrtype - -*-- AIR =IiUNCTION- -

downstream location AIRSPACE upstream environment downstream Control Room has filter false flow rate Time (hr) Value (cfm) 48 3700 endflow rate endjunction junction junction type AIR JUNCTION downstream location AIR-SPACE upstream Control_Room downstream environment has filter false flow rate Time (hr) Value (cfm) 48 3700 end-flowrate X_over_Q 4 ctrl room Time (hr) Value (s/m*3) 48 0 end X over_Q_4_ctrlroom XoverQ_4_siteboundary Time (hr) Value (s/m*3) 48 0 end X overQ_4_site_boundary X_over_Q_4_low_population zone Time (hr) Value (s/m*3) 48 0 endX_over_Q_4_low populationzone endjunction environment breathing rate sb Time (hr) Value (cms) 24 0.0 26 0.00035 48 0.0 end breathing_rate sb breathingrate lpz Time (hr) Value (cms) 48 0.0 end breathing rate lpz endenvironment

PSAT 3019CF.QA.05 Attachment A INPUT.DAT, 24 br, 20%h Rev 0 edittime 0.0 0.01 23.9833 24.0 48.0 endedittime participatingisotopes Krg3m Kr85m Kr85 Kr .7 Kr8B Kr89 Xel31m Xel33m Xel33 Xe:13 Sm Xel35 Xel37 Xe138 1131Org 1l320rg II:33 rg 11340rg 113 S0rg Tel31m Te132 endjparticipatingisotopes core thermalpower 1950

... ;' -.--b ,. . . . ..i ... ....

'iilit mental iodine frac .....

organic iodine -frac 1.0 particulate iodinefrac 0.0 release frac to controlvolume GAP Time NGas IGrp CSGrp TeV3rP BaGrp NM4tls CeGrp LaGrp SrGrp 0.01 8.25 6.25 0 e.: 25 0 0 0 0 0 48 0 0 0 0 0 0 0 0 0 endtocontrolvolume endrelease frac end-core control volume obj_type OBJ CV name GAP air volume 100 water volume 0 surfacearea has recirc filter false end control volume controlvolume obj_type OBJCV name RB air volume 100 water volume 0 surface area 0 has recirc filter false endcontrol volume control volume objtype OBJ CR name Control Room air volume 4.15e+004 water volume 0 surfacearea 0 hasrecirc filter false breathing rate Time (hr) Value (cms) 48 0.00035 end breathing rate occupancy_factor Time (hr) Value (frac) 48 1 end occupancy factor end control volume junction

PSAT 3019CF.QA.05 Attachment A INPUTTDAT, 24 hr, 20%

Rev 0 junction type AIR JUNCTION downstream-location AIRSPACE upstream CORE downstream GAP has filter false flow rate Time (hr) Value (cfm) 48 1 end flow rate endjunction junction junction type AIR JUNCTION downstream location -* AIRSPACB -

upstream GAP downstream RB has filter true flow rate Time (hr) Value (cfm) 23.9633 0 24 0.571 48 0 endflowrate filter_efficiency Time NobleGas Elemlodine OrgIodine PartIodine Solubles Insolubles 48 0 0 0.995 0 0 0.99999 endfilter efficiency frac 4 daughter resusp Time NobleGas Elemlodine OrgIodine PartIodine Solubles Insolubles-48 0 0 0 0 0 0 end frac_4 daughterresusp reevolution rate Time NobleGas ElemIodine OrgIodine PartIodine Solubles Insolubles 48 0 0 0 0 0 0 end reevolution rate endjunction junction junction-type AIR_JUNCTION downstreamlocation AR_SPACE upstream RB downstream environment hasfilter false flow rate Time (hr) Value (cfm) 24 0 24.1 3.84 24.6 1.25 25.1 2 26 6.5 120 0 end flow-rate X_over_Q_4 site boundary Time (hr) Value (s/r*3) 24 0 24.1 1.7e-3 24.6 2.03e-4 25.1 1.54e-4 26 9.17e-5 48 0.0 end_X over_Q_4_site-boundary

PSAT 3019CF.QA.05 Attachment A INPUTDAT, 24 hr, 20%

Rev 0 X_over Q 4_lowypopulation zone Time (hr) Value (s/m*3) 48 0.0 end Xover-Q.4_lowyopulation zone k_overQ_4 ctrlroom Time (hr) Value (s/m*3) 24 0.0 24.1 5.89e-3 24.6 2.39e-4 25.1 1.05e-6 26 8.70e-7 48 0.0 end XoverQ_4 ctrl room endjunction .... ........ -.

junction junction-type AIRJUNCTION downstream location AIRSPACE upstream environment downstream ControlRoom has filter false flow_rate Time (hr) Value (cfm) 48 3700 end-flowrate endj unction junction junction type AIRJUNCTION downstreamlocation AIR_SPAQE upstream Control.Room downstream environment has filter false flow rate Time (hr) Value (cfm) 48 3700 endflow-rate X-overQ 4 ctrl room Time (hr) Value (s/m*3) 48 0 end X overQ_4_ctrlroom X_over_Q_4 site boundary Time (hr) Value (s/m*3) 48 0 endX over Q_4_site-boundary X_over _Q_4_low-population zone Time (hr) Value (s/m*3) 48 0.

end_X-overQ_4 lowpopulationzone endjunction environment breathingratesb Time (hr) Value (cms) 24 0.0 26 0.00035 48 0.0 end breathingrate-sb breathing ratelpz Time (hr) Value (cms) 48 0.0

PSAT 3019CF.QA.05 Attachment A INPUT.DAT, 24 hr, 20%

Rev 0 endbreathing rate lpz end environment

PSAT 3019CF.QA.05 Attachnent A INPUTDAT, 96 hr, 0%

Rev 0 edit time 0.0 0.01 95.9e33 96.0 120.0 endedit-time participatingisotopes Kr83m Kr85m Kr85 Kr87 Kr88 IKrB.9 Xel31m Xel33m Xel33 Xe135m Xel35 Xel37 Xe£38 11310rg 11320rg Ii330rg 113 40rg 113 50rg Tel31m Tel32 end participating isotopes core thermalpower 1950 elemental iodine frac . 0.0 organiciodine frac 1.0

-particulate iodine frac 0.0 release frac to controlvolume GAP Time N Gas I-Grp CsGrp Tel:rp BaGrp NMtls CeGrp LaGrp SrGrp 0.01 8.25 8.2S 0 8.:25 0 0 0 0 0 120 0 0 0 0 0 0 0 0 0 endto controlvolume end release_frac endcore control volume obj type OBJ CV name GAP air volume 100 water volume 0 surface area 0 has recircfilter false end control volume control volume obj_type OBJCV name RB air volume 100 water volume 0 surface area 0 hasrecirc filter false end control volume controlvolume obj type OBJ CR name Control_Room airvolume 4.15e+004 water volume 0 surface area 0 has recirc filter false breathing rate Time (hr) Value (cms) 120 0.00035 endbreathingrate occupancy factor Time (hri Value (frac) 120 1 endoccupancyfactor end control volume junction

PSAT 3019CF.QA.05 Attachment A4 - INPUT.DAT, 96 hr. 0%

Rev 0 junction type AIR JUNCTION downstream location AIR SPACE upstream CORE downstream GAP hasfilter false flow rate Time (hr) Value (cfm) 120 1 end-flow rate endjunction junction junction type AIR JUNCTION Jdownstteamlocation AIRSPACE --

= -- - : ;-.-.

upstream GAP downstream RB has filter true flowrate Time (hr) Value (cfm) 95.9833 0 96 0.571 120 0 end flow rate filter efficiency Time NobleGas Elemlodine OrgIodine PartIodine Solubles Insolubles 120 0 0 0.995 0 0 0.99999 endfilterefficiency frac_4_daughter resusp Time NobleGas ElemIodine OrgIodine PartIodine Solubles Insolubles 120 0 0 0 0 0 0 end frac_4_daughter resusp reevolution rate Time Noble~as ElemIodine OrgIodine PartIodine Solubles Insolubles 120 0 0 0 0 a 0 end reevolution rate end_junction junction junction_type AIR JUNCTION downstream location AIRSPACE upstream RB downstream environment has filter false flowrate Time (hr) Value (cfm) 96 0 96.5 0.96 97 1.335 98 6.5 120 0 end flow rate X overQ 4 site boundary Time (hr) Value (s/m*3) 96 0 96.5 2.03e-4 97 1.54e-4 98 9.17e-5 120 0.0 end_X_over_Q_4_site boundary X over Q_4lowpopulationzone Time (hr) Value (s/m*3)

PSAT 3019CF.QA.05 Attachment A INPUTDAT, 96 hr. 0%/a Rev 0 120 0.0 end X over Q 4_low population zone X_over_Q_4_ctrl room Time (hr) Value (s/m*3) 96 0.0 96.5 2.39e-4 97 1.05e-6 98 8.70e-7 120 0.0 end_X over_Q_4_ctrlroom end_junction junction

.unct-iontype - .. . AIR JUNC N. . .-

downstream-location AIRSPACE upstream environment downstream Control Room has filter false flowrate Time (hr) Valile (cfm) 120 3V700 endflowrate endjunction junction junction type AIR JUNCTION downstream location AIRSPACE upstream Control Room downstream environment has filter false flowv rate Time (hr) Value (cfm) 120 3700 end flowrate X overQ4_ctrl room Time (hr) Value (s/m*3) 120 0 endkXover_Q4 ctrl room X_over Q 4 site boundary Time (hir) - Value (s/m*3) 120 0 end XoverQ_4_site boundary X_over Q_4 low populationzone Time (hr) Value (6/m*3) 120 0 endX over_Q. 4_low population zone end junction -

environment breathingrate sb Time (hr) Value (cms) 96 0.0 98 0.00035 120 0.0 end breathingrate ab breathing rate lpz Time (hr) Value (cms) 120 0.0 end breathingrate lpz endenvironment

PSAT 3019CF.QA.05 Attachment A INPUT.DAT, 96 hr, 20%

Rev 0 junction type AIR JUNCTION _

downstream location AIRSPACE upstream CORE downstream GAP has filter false flow rate Time (hr) value (cfm) 120 1 end flow-rate end junction junction junction type AIR_JUNCTION

--downstxream.4ocation -- s .:

upstream GAP downstream RB has filter true fllow_rate Time (hr) Value (cfm) 95.9833 0 96 0.571 120 0 end flow rate filter_efficiency Time NobleGas ElemIodine OrgIodine PartIodine Solubles Insolubles 120 0 0 0.995 0 0 0.99999 endfilter-efficiency frac 4daughter resusp Time NobleGas Elemlodine OrgIodine PartIodine Solubles Insolubles 120 0 0 0 0 0 0 end frac_4_daughter resusp reevolution rate Time Noble as ElemIodine OrgIodine PartIodine Solubles Insolubles 120 0 0 0 0 0 0 end reevolution rate endjunction junction junction-type AIR JUNCTION downstream-location AIR_SPACE upstream RB downstream environment hasfilter false flow rate Time (hr) Value (cfm) 96 0 96.1 3.84 96.6 1.25 97.1 2 98 6.5 120 0 end flow-rate X_over_Q_4_site-boundary Time (hr) Value (s/m*3) 96 0 96.1 1.7e-3 96.6 2.03e-4 97.1 1.54e-4 98 9.17e-5 120 0.0 end_X_over_Q_4_site boundary

PSAT 3019CF.QA.05 Attachment A INPUT.DAT, 96 hr, 20%

Rev 0 edit time 0.0 0.01 95.9833 96.0 120.0 end edittime participatingisotopes Kr83m Kr8Sm Kr8S Kr87 Kr88 KrB9 Xel31m Xel33m Xe133 Xe135m Xel35 Xel37 Xel38

}1310rg 11320rg I1330rg 11340rg I1350rg Tel31m Tel32 end participating isotopes core thermal_power 1950

-:=. ., V~-: 'sT; .elemental iodine frac _--.z , .. :-.

'- ..5 - . . ..

organic iodine frac 1.0 particulate iodine frac 0.0 release frac to controlvolume GAP Time N Gas I Grp CsGrp TeGrp BaGrp NMtls CeGrp LaGrp SrGrp 0.01 8.25 8.25 0 8.25 0 0 0 0 0 120 0 0 0 0 0 0 0 0 0 end to control volume end release frac endcore control volume obj. type OBJ CV name GAP air volume 100 watervolume 0 surface area 0 hasrecirc filter false end control volume control volume obj_ type OBJCV name RB air volume 100 watervolume 0 surface area 0 has recircfilter false endcontrolv olume controlvolume obj type OBJ CR name ControlRoom air volume 4.15e+004 water volume 0 surface area 0 has recirc filter false breathing rate Time (hr) Value ( Icms) 120 0.00( 035 end breathing rate occupancy factor Time (hr) Value! (frac) 120 1 endoccupancy factor end control volume junction

PSAT 3019CF.Qk05 Attachment A NPUT.DAT, 96 hr. 0%

Rev 0 junctiontype AIR JUNCTION downstream location AIR_SPACE upstream CORE downstream GAP has filter false flow-rate Time (hr) Value (cfm) 120 1 endflow-rate endjunction junction junction type AIR JUNCTION

.. z::._:downgttrekiulocation ...............

AIRCSPACE :-- -. - . ..- --

upstream GAP downstream RB has filter true flow rate Time (hr) Value (cfm) 95.9B33 0 96 0.571 120 0 end-flow rate filter-efficiency Time NobleGas Elemlodine OrgIodine PartIodine Solubles Insolubles 120 0 0 0.995 0 0 0.99999 endfilterefficiency frac 4 daughterresusp Time NobleGas Elemlodine OrgIodine PartIodine Solubles Insolubles 120 0 0 0 0 0 0 end frac_4 daughter resusp reevolution rate Time NobleGas Elemiodine OrgIodine PartIodine Solubles Insolubles 120 0 0 0 0 0 0 enddreevolutionrate endjunction junction junctiontype AIR JUNCTION downstreamlocation AIRsPACE upstream RB downstream environment basfilter false flow rate Time (lhr) Value (cfm) 96 0 96.5 0.96 97 1.335 98 6.5 120 0 end-flow rate X2over_Q_4 site boundary Time (hr) Value (s/m*3) 96 0 96.5 2.03e-4 97 1.54e-4 98 9.17e-5 120 0.0 end X over Q3_site boundary X)over_Q_4_lowypopulationzone Time (hr) Value (s/M*3)

I.. .... .

PSAT 3019CF.QA.05 Attachment A4 - NPULT.DAT, 96 hr, 0%

Rev 0 120 0.0 end_X_over_Q_4_lowpopulationzone X_overQ_4 ctrlroom Time (hr) Value (s/m*3) 96 0.0 96.5 2.39e-4 97 1.OSe-6 98 8.70e-7 120 0.0 end_X_overQ_4_ctrl room end2junction junction junctoiontype . AIR. JUNCTION . -.

downstreamlocation AIR SPACE upstream environment downstream Control Room hasfilter false flowrate Time (hr) Value (cfm) 120 3700 endflow rate endjunction junction junction type AKR_JUNCTION downstreamlocation AIRSPACE upstream Control Room downstream environment has filter false flow rate Time (hr) Value (cfm) 120 3700 end-flow rate XoverQ_4_ctrl room Time (hr) Value (s/m*3) 120 0 end-X-over_Q_4_ctrl room X_over_Q_4_site boundary Time (hr) Value (s/m*3) 120 0 end X overQ_ 4_site boundary kXoverQ4_lowjpopulation zone Time (hr) Value (s/m*3) 120 0 endX over_Q_4_low_population zone endjunction environment breathingratesb Time (hr) Value (cms) 96 0.0 98 0.00035 120 0.0 end breathing_rate_sb breathingrate lpz Time (hr) Value (cms) 120 0.0 endbreathingrate lpz end-environment

PSAT 3019CF.QA.05 Attachment A INPUT.DAT, 96 hr, 200%

Rev 0 junction type AIR JUNCTION _

downstream location AIR SPACE upstream CORE downstream GAP has filter false flowrate Time (hr) Value (cfm) 120 1 end flow rate endjunction junction junction type AIR JUNCTION

-.downst-ream.-location. ..--n AIR_ SPACE . - -..

upstream GAP downstream RB has filter true flow rate Time (hr) Value (cfm) 95.9833 0 96 0.571 120 0 end flow rate filter efficiency Time NobleGas ElemIodine OrgIodine PartIodine Solubles Insolubles 120 0 0 0.995 0 0 0.99999 end filter efficiency frac_4_daughter resusp Time NobleGas Elemlodine Orgrodine PartIodine Solubles Insolubles 120 0 0 0 0 0 0 end frac 4 daughter resusp reevolution rate Time Noblecas Elemlodine OrgIodine PartIodine Solubles Insolubles 120 0 0 0 0 0 0 end reevolutionrate endjunction junction junction type AIRJUNCTION downstream location AIRSPACE upstream RB downstream environment has filter false flow_rate Time (hr) Value (cfm) 96 0 96.1 3.84 96.6 1.25 97.1 2 98 6.5 120 0 end flow rate X_over_Q4_site boundary Time (hr) Value (s/m*3) 96 0 96.1 1.7e-3 96.6 2.03e-4 97.1 1.54e-4 98 9.17e-5 120 0.0 end_X overQ 4_site boundary

PSAT 3019CF.QA.05 Attachmnent A-S - INPUT.DAT, 96 hr, 20%

Rev 0 X_overQ_4_low population zone Time (hr) Value (s/m*3) 120 0.0 end_X-overQ_4_lowjpopulation zone X over_Q_4_ctrl room Time (hr) Value (s/m*3) 96 0.0 96.1 S.89e-3 96.6 2.39e-4 97.1 l.05e-6 98 8.70e-7 120 0.0 end X over_Q__4ctrlroom end junction ..

junction junction type AIR JUNCTION downstream location AIR_SPACE upstream environment downstream Control Room has filter false flow_rate Time (hr) Value (cfm) 120 3700 end flow rate endjunction junction junctiontype AIRJUNCTION downstream location AIR_SPACE upstream Control Room downstream environment has filter false flow_rate Time (hr) Value Wcfm) 120 3700 end flowrate X_over Q 4 ctrl room Time (hr) Value Is/m*3) 120 0 endX-over_Q_4_ctrlroom X overQ_4_site boundary Time (hr) Value (e/m*3) 120 0 end X over Q_4 site boundary X over_Q_4_lowpopulation zone Time (hr) Value (s/m*3) 120 0 endXXoverQ.4_low0wopulationzone end junction environment breathing rate eb Time (hr) Value (cms) 96 0.0 98 0.00035 120 0.0 end breathing_rate_sb breathing rate lpz Time (hr) Value (cms) 120 0.0

PSAT 301 9CF.QA.05 Attachment A INPUT.DAT, 96 hr, 20%

Rev 0 edittime 0.0 0.01 95.9833 96.0 120.0 endedittime participating isotopes Kr83m Kr85m Kr85 Kr87 ,Kr8B Kr89 Xel31m Xel33m Xel33 Xel35m Xe135 Xe137 Xel38 I1310rg I1320rg 11330rg 113 4 rg I1350rg Tel3lm Tel32 end participating isotopes core thermal_power 1950

..- "I s .elementaliodinefrac, .. S_ _ 9-.. . : . ,7~ '; .y.*, . .I... . .

organiciodine frac 1.0 particulate iodine frac 0.0 releasefrac to control volume GAP Time N Gas I Grp CsGrp TeGrp BaGrp NMtls CeGrp LaGrp SrGrp 0.01 8.25 8.25 0 8.25 0 0 0 0 0 120 0 0 0 0 0 0 0 0 0 endto control volume end release frac endcore controlvolume obji type OBJCV name GAP air volume 100 water volume 0 surface area 0 has recirc filter false end control volume control volume obj_ 'type OBJ CV name RB airvolume 100 water volume 0 surface area 0 has recirc filter f alse endcontrol volume control volume obj_type OBJ CR name Control Room airvolume 4.15e+0O04 water volume 0 surface area b has recirc filter false breathingrate Time (hr) Value (cms) 120 0.00035 end breathingrate occupancyjfactor Time (hr) Value (frac) 120 1 end occupancy factor end controlvolume junction

PSAT 3019CF.QA.05 Attachment A INPUTDAT, 96 hr, 200%

Rev 0 end breathing rate lpz end environment

PSAT 3019CF.QA.05 Page BI of 1 Rev 0 Appendix B - Minimum Decay Time Giving Acceptable Control Room Dose Results without Credit for Containment From the main body of the calculation, one may note that for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of decay, about 88% of the control room dose is from 1131 (Tables 3 and 4). With 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months of decay, it is 98% (Tables 5 and 6). At even later decay times (decay times that will give acceptable control room doses without any credit for containment), one may assume that the control room dose will be due entirely to I13 1.

r' go*~'.~; ' *AtS96.ours thWeC Rdose is 2.2 rem with-200/ ground-level release (Table 6). Nearly all of this 2.2 rem (except for less than 0.1 rem) is due to that 20% ground-level contribution. Therefore, the dose for 100/o ground-level release would be about 11 rem (very slightly conservative) at 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months . To have the control room dose be less than the 5 rem control room dose limit at some later time, the 1131 release would have to decrease to 511l (i.e., to 45%) of its inventory at 4 days. With a decay constant of about IE-6 per second, this would require about 8E5 seconds or just over 9 days. Therefore, with a measure of conservatism, it can be confidently asserted that no containment would be needed after 14 days from the time of shutdown to have the control room dose be less than the 5 rem TEDE limit for the FHA.

QAP 6.1 Revision 0 4/28/95 Attachment 4 Form QA-007 Document TransmittallRecelpt

- '. "7- T

-I -, Pedro Perez Date: 6/24/03 Vermont Yankee From: Dave Leaver

Subject:

Fuel Handling Accident Dose for Vermont Yankee, PSAT 3019CF.QA.05, Revision 0 Controlled Copy P. 3 Please acknowledge receipt of the enclosed (ControlledNerified) Copy by signing on the line provided and returning this form to the Document Controller at the address shown below. This form must be received by the Document Controller on or before 7/11/03 in order for the document to remain in controlled status.

Name: 6a 6 Date: _/___3 Return to:

Julie Loya Polestar Applied Technology, Inc.

One First Street Suite 4 Los Altos, CA 94022 N I

QAP 6. 1 Revision 0 4/28/95 Attachment 1 Form QA-023 Polestar Applied Technology, Inc.

DOCUMENT CUSTODY FORM DOCUMENT: Fuel Handling Accident Dose for Vermont Yankee.

PSAT 3019CF.QA.05 ASSIGNED TO Name: Pedro Perez Organization: Vermont Yankee Nuclear Power Station Address: 320 Governor Hunt Road Vernon. VT 05354-9767 CONTROLLED COPY NUMBER 3 ASSIGNED BY Dave Leaver When this document is no longer required, please handle as Indicated below:

E] Return to: E] Destroy Polestar Applied Technology, Inc.

.One First Street Suite 4 Los Altos, CA 94022 Attention: (Name of Document Controller)

I

ML032190656

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