Text

Calculation, Pool Handling Accident Dose for Vermont Yankee, Psat 3019CF.QA.05
	ML032190656
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
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
	Download: ML032190656 (40)
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PSAT 3019CF.QA.05 Pg2 of 13 Rev 0 Table of Contents Section Purpose Summary of Results Methodology Assumptions References Design Inputs Calculation Results Conclusions Page 2

2 3

3 4

4 5

7 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 of Dose 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 (1l half-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 (2nd 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 to the 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 Br83 4.24E+03 Kr83m 4.24E+03 Br85 9.61E+03 Kr85m 9.71E+03 Kr85 5.05E+02 ICr87 1.94E+04 Kr88 2.75E+04 Er89 3A6E+04 Tel31m 4.31E+03 1131 2.85E+04 Xe131m 3.18E+02 Tel32 3.97E+04 1132 4.05E+04 Tcl33m 2.30E+04 Tel33 3.39E+04 1133 5.79E+04 Xel33m 1.76E+03 Xel33 5.78E+04 Te134 5.3lE+04 1134 6A3E+04 1135 5.39E+04 Xel35m 1.14E404 Xel35 2.33E+04 Xe137 5.07E+04 Xel38 5.05E+04

Considered as parent only Adjusted 24 Hours 96 Hours same same 1.OIE+03 same same s

4.56E+04 same same same sanE same same same same same same same 15.6 negligible 239 1010 0.038 72.3 negligible 42105 327 33065 26656 1594 55528 negligible 4351 negligible 15285 negligible negligible negligible 1009 negligible negligible negligible 32776 338 17466 2420 766 40184 negligible 2.3 negligible 106 negligible negligible 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):

Stack (norm):

RB siding:

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

XIQs Power=

1950 CR Vol = 41533.75 Rel Frac. =

2.85E-04 Pealing=

1.65 Nuclide Ci/MW Kr83m.

-.1,56B+01 Kr85m 2.39E+02 Kr85 1.01E+03 Kr87 3.80E-02 Kr88 7.23E+01 Kr89 0.OOE+00 Xel3lm 0.OOE+00 Xel33m 0.OOE+00 Xel33 5.30E+04 Xel35m 0.OOE+00 Xel35 1.45E+04 XeI37 0.OOE+00 Xel38 O.OOE+00 11310rg 4.21E+04 11320rg 3.31E+04 11330rg 2.67E+04 11340rg 0.OOE+00 11350rg 4.35E+03 I131EIem 4.21E+04 I132Elem 3.31E+04 I133Elem 2.67E+04 I134Elem O.OOE+00 1135Elem 4.35E+03 EAB 1.35E-04 MWt ft3 WB DCF 1.49E-05 0.0277 4.40E-04 0.1524 0.3774 0.323 0.00149 0.00507 0.00577 0.07548 0.04403 0.0303 0.199 0.06734 0.4144 0.10878 0.481 0.3069 0.06734 OA144.

0.10878 0.481 0.3069 CR 6.04E-05 CEDE DCF

. 0 0

0 0

0 32893 381.1 5846 131.35 1228.4 32893 381.1 5846 131.35 1228A sec/m3 (0°/e release at ground level)

TEDE DCF

.1.5E-95.

0.0277 0.00044 0.1524 0.3774 0.323 0.00149 0.00507 0.00577 0.07548 0.04403 0.0303 0.199 11.5799 0.54779 2.15488 0.52697 0.73684 11.5799 0.54779 2.15488 0.52697 0.73684 CR TEDE DCF 5E-07 0.0009 lE-05 0.0047 0.0117 0.01 5SE-05 0.0002 0.0002 0.0023 0.0014 0.0009 0.0062 11.515 0.1462 2.0495 0.0609 0.4395 11.515 0.1462 2.0495 0.0609 0.4395 Total TEDE=

EAB TEDE 9Q.O00 0.00082 0.00006 0.00000 0.00338 0.00000 0.00000 0.00000 0.03787 0.00000 0.07903 0.00000 0.00000 0.09054 0.00336 0.01067 0.00000 0.00060 0.21147 0.00786 0.02491 0.00000 0.00139 0.47194 CR TEDE 0.00000 0.00001 0.00000 0.00000 0.00005 0.00000 0.00000 0.00000 0.00053 0.00000 0.00110 0.00000 0.00000 0.04028 0.00040 0.00454 0.00000 0.00016 0.09408 0.00094 0.01060 0.00000 0.00037 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)

Ground Level XJQs =

Power=

1950 CR Vol = 41533.75 Rel Fract =

2.85E-04 Pealing =

1.65 Nuclide Ci/MW Z

r~

1.56E+01 Kr85m 2.39E+02 Kr85 1.O1E+03 Kr87 3.80E-02 Kr88 7.23E+01 Kr89 O.OOE+00 Xel3lm O.OOE+OO Xei33m 0.OO+o00 Xel33 5.30E+04 Xel35m O.OOE+OO Xel35 1.45E+04 Xe137 O.OOE+00 Xel38 0.OOE+00 I13lOrg 4.21E+04 11320rg 3.31E+04 11330rg 2.67E+04 11340rg 0.00E+00 11350rg 4.35E+03 I131Elem 4.21E+04 I132Elem 3.31E+04 I133EIem 2.67E+04 I134Elem 0.OOE+OO I135Elem 4.35E+03 EAB 4.57E-04 MW(t) f3 WB DCF 1.49E-05 0.0277 4.40E-04 0.1524 0.3774 0.323 0.00149 0.00507 0.00577 0.07548 0.04403 0.0303

0.199 0.06734 0.4144 0.10878 OA81 0.3069 0.06734 0.4144 0.10878 0.481 0.3069 CR 1.24E-03 sec/m3 (20% release at ground level)

CEDE TEDE CR TEDE DCF DCF DCF

- °.I.SE-05

._Ei97 0

0.0277 0.0009 0

0.00044 IE-05 0

0.1524 0.0047 0

0.3774 0.0117 0

0.323 0.01 0

0.00149 SE-05 0

0.00507 0.0002 0

0.00577 0.0002 0

0.07548 0.0023 0

0.04403 0.0014 0

0.0303 0.0009 0

0.199 0.0062 32893 11.5799 11.515 381.1 0.54779 0.1462 5846 2.15488 2.0495 131.35 0.52697 0.0609 1228A 0.73684 0.4395 32893 11.5799 11.515 381.1 0.54779 0.1462 5846 2.15488 2.0495 131.35 0.52697 0.0609 1228.4 0.73684 0.4395 Total TEDE EAB TEDE

-QtQOM 0.00277 0.00019 0.00000 0.01143 0.00000 0.00000 0.00000 0.12820 0.00000 0.26754 0.00000 0.00000 0.30648 0.01139 0.03611 0.00000 0.00202 0.71585 0.02659 0.08433 0.00000 0.00471 1.59761 CR TEDE 0...0,00 0.00023 0.00002 0.00000 0.00096 0.00000 0.00000 0.00000 0.01079 0.00000 0.02252 0.00000 0.00000 0.82691 0.00825 0.09318 0.00000 0.00326 1.93140 0.01926 0.21763 0.00000 0.00762 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)

Ground Level XlQs =

Power=

1950 CR Vol = 41533.8 Rel Frac. = 2.85E-04 Peaking =

1.65 Nuclide Ci/MW EAB CR 1.35E-04 6.04E-05 sec/m3 (0%/o release at ground level)

MWt ft3 Kr83m Kr85m Kr85 Kr87 Kr88 Kr89 Xel31m Xel33m Xel33 Xel35m Xe135 Xe137 Xel38 11310rg 11320rg 11330rg 11340rg 11350rg I131Elem I132Elem I133Elern I134Elemn I135Elern 0

1009 0

0 0

338 766 40184 0

106 0

0 -

32776 17466 2420 0

2.3 32776 17466 2420 0

2.3 WB DCF

-1.49E-05 0.0277 4.40E-04 0.1524 0.3774 0.323 0.00149 0.00507 0.00577 0.07548 0.04403 0.0303 0.199 0.06734 OA144 0.10878 0.481 0.3069 0.06734 0.4144 0.10878 0.481 0.3069 DCF

.;0- ;

0 0

32893 381.1 5846 13 1.35 1228.4 32893 381.1 584 131.35 1228.4 CEDE TEDE DCF

.1,51Q5 0.0277 0.00044 0.1524 0.3774 0.323 0.00149 0.00507 0.00577 0.07548 0.04403 0.0303 0.199 11.5799 0.54779 2.15488 0.52697 0.73684 11.5799 0.54779 2.15488 0.52697 0.73684 CR TEDE DCF 7 -

0.0009 E-S05 0.0047 0.0117 0.01 SE-05 0.0002 0.0002 0.0023 0.0014 0.0009 0.0062 11.515 0.1462 2.0495 0.0609 0.4395 11.515 0.1462 2.0495 0.0609 0.4395 Total TEDE=

EAB TEDE 40000 0.00000 0.00005 0.00000 0.00000 0.00000 0.00006 0.00048 0.02871 0.00000 0.00058 0.00000 0.00000 0.07048 0.00178 0.00097 0.00000 0.00000 0.16461 0.00415 0.00226 0.00000 0.000(0 0.27413 CR TEDE 0.0000.

0.00000 o.o00 0.00000 0.00000 0.00000 0.00000 0.00001 0.00040 0.00000 0.00001 0.00000 0.00000 0.03135 0.00021 0.00041 0.00000 0.00000 0.07323 0.00050 0.00096 0.00000 0.00000 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)

Ground Level X/Qs =

Power =

CR Vol =

Rel Fract -

Peaking =

Nuclide KEr83m*

Kx85m Kr85 Kr87 Kr88 Kr89 Xel3im Xel33m Xel33 Xel35m Xel.35 Xel37 Xe138 11310rg 11320rg 11330rg 11340rg 11350rg I131Elem I132Elem I133Elem I134EIem 1135Elem 1950 41533.8 2.85E-04 1.65 Ci/MW 0

1009 0

0 0

338 766 40184 0

106 0

32776 17466 2420 0

2.3 32776 17466 2420 0

2.3 EAB 4.57E-04 MW(t) ft3 WB DCF 49E&05 0.0277 4.40E-04 0.1524 0.3774 0.323 0.00149 0.00507 0.00577 0.07548 0.04403 0.0303 0.199 0.06734 0.4144 0.10878 0.481 0.3069 0.06734 OA144 0.10878 0.481 0.3069 CEDE TEDE DCF DCF

- 1.5EB 1)-

0 0.0277 0

0.00044 0

0.1524 0

0.3774 0

0.323 0

0.00149 0

0.00507 0

0.00577 0

0.07548 0

0.04403 0

0.0303 0

0Q199 32893 11.5799 381.1 0.54779 5846 2.15488 131.35 0.52697 1228.4 0.73684 32893 11.5799 381.1 0.54779 5846 2.15488 131.35 0.52697 1228.4 0.73684 CR DCF

-E-07--

0.0009 IE-05 0.0047 0.0117 0.01 SE-OS 0.0002 0.0002 0.0023 0.0014 0.0009 0.0062 11.515 0.1462 2.0495 0.0609 0.4395 11.515 0.1462 2.0495 0.0609 0.4395 Total TEDE EAB TEDE 0.00000 0.00000 0.00019 0.00000 0.00000 0.00000 0.00021 0.00163 0.09720 0.00000 0.00196 0.00000 0.00000 0.23858 0.00601 0.00328 0.00000 0.00000 0.55723 0.01405 0.00766 0.00000 0.00000

=

0.92799 CR TEDE A"Q00000;.

0.00000 0.00002 0.00000 0.00000 0.00000 0.00002 0.00014 0.00818 0.00000 0.00016 0.00000 0.00000 0.64369 0.00436 0.00846 0.00000 0.00000 1.50345 0.01018 0.01976 0.00000 0.00000 2.19841 CR 1.24E03 sechn3 (20%/o release at ground level)

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.tol t 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*

Kr83m 15.6 Kr18m 239 Kr85 1010 Kr87 0.038 KrM8 72.3

-. Kr89 ~-

eglwgb'e 1131 42105 Xel31m 327 1132 33065 1133 26656 Xel33m 1594 Xel33 55528 I134 negligible 1135 4351 Xel3Sm negligible Xel35 15285 Xe137 negligible Xel38 negligible

Main body of calculation

- STARDOSE 24 Hours**

96 Hours*

96 Hours**

I negligible 0

219 negligible 0

1007 1009 1007 0.04 negligible 0

72 negligible 0

-7 negligible 42207 32776 32883 300 338 252 32945 17466 17218 26107 2420 2393 1299 766 527 55571 40184 40466 O

negligible 0

4563 2.3 3

0 negligible 0

15540 106 116 0

negligible 0

0 negligible 0

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

ControlRoom Total dose:

Noble gas Org iodine thyroid 4.90E+000 0.00E+000 4.90E+000 wbody

1. 92E-003 1.75E-003 1.63E-004 skin 8.89E-002 8.69E-002 1.98E-003 CEDE 1.51E-001

o. OOE+000

1. S1E -001 environment thyroid wbody skin CEDE 1.05E+001 1.31E-001 1.89E-001 3.24E-001 EAB dose:

Noble gas Org iodine thyrdeab

0. 00E+000 I. 05E+001 wbodyjeab 1.20E-001

1. 08E-002 skin eab 1.85-001 4.09E-003 CEDE eab 0.001+000 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 Total dose:

Noble gas Org iodine thyroid

1. 03E+002

0. OOE+000

1. 03E+002 wbody 4.OBE-002 3.73E-002 3.57E-003 skin 1.69E+O0o 1.84E+000 4.27E-002 CEDE

3. 18E+o00 O.OOE+000

3. 18E+000 environment

"-B do4 se:

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

E+0 0 0

^ ;

EAB dose:

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

ControlRoom Total dose:

Noble gas Org iodine thyroid 3.50E+000 0.OOE+000

3. 50E+000 wbody 4.91E-004 4.16E-004 7.52E-005 skin 2.75E-002 2.67E-002 7.94E-004 CEDE 1.07E-001

0. OOE+000 1.07E-001 environment EAB dose:

Noble gas Org iodine thyroid 7.52E+000 thyrdeab

0. OOE+000 7.52EB000 wbody 3.38E-002 wbody eab 2.88E-002

4. 94E-003 skin 5.91E-002 skin eab 5.75E-002 1.63E-003 CEDE 2.30E-001 CEDE eab 0.OOE+000 2.30E-001 Excerpt from STARDOSE output correspondint to Attachment 5 INPUT2DAT (20% ground-level release, 96-hour decay):

Control-Room Total dose:

Noble gas Org iodine thyroid 7.36E+001

0. OOE+000 7.36E+001 wbody 1.04E-002 8.75E-003 1.64E-003 skin

5. SE-001 5.63E-001 1.73E-002 CEDE 2.25E+000 0.OOE+000 2.25E+000 environment thyroid wbody skin CEDE 2.64E+001 1.20E-001 2.08E-001 8.OSE-001 EAB dose:

Noble gas Org iodine thyrd eab O.OOE+000 2.64E+001 wbodyeab 1.OlE-001

1. 92E-002 skin eab 2.02E-001 6.22E-003 CEDE eab 0.OOE+000 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 n-isotopes 20 Kr83m N Gas NONE 0

0 KrSSm N Gas NONE o

0 KrB5 NGan NONE o

o Kr87 N Gas NONE 0

0 Kr88 N Gan NONE o

0 Kr89 N Gan NONE 0

0 Xel3lm N Gas o

0 Xel33m N Gas 0

0 Xel33 N Gas I1330i o

o Xel35m N Gan 0

0 Xel35 N Gan I135O1 0

0 Xel37 N Gan NONE 0

o Xel38 N Gas NONE o

0 I1310rg OrgI 0.13 0

11320rg Org I 0

0 I1330rg OrgI o

0 11340rg OrgI 0

0 I1350rg Org.I 0

0 Tel3lm TeGrp 0

0 Tel32 TeGrp NONE 0

0 Attai.sent A LIBFILEI.TXT Rev 0 n_isotopegroups 11 NONE 4.242+03 1.042-04 0

0 NONE 9.71E+03 4.39E-OS 0

0 NONE 1.01E+03 2.04B-09 0

0 NONE 1.94El04 1.52B-04 0

0 NONE 2.75B+04 6.882-05 0

0 NONE 3.46E+04 3.63E-03 0

NONE NONE 3.18E+02 6.682-07 0

0 NONE NONE 1.76E203 3.492-06 o

-o rg

,INONE 5.78E+04 1.52E-06 0

NONE !NONE 1.14E+04 7.40E-04 O

0 rg MNONE 2.332+04 2.09E-05 o

'0 NONE 5.07E+04 2.96B-03 0

0 NONE 5.SE+04 6.80E-04 0

96E-1.49E-05 0

0 0

0.0277 0

0 0.05 4.402-04 0

0 0.05 0.1524 0

0 0.34 0.3774 0

0 0.08 0.323 0 0

0.35 0

0 0.00149 0

0 0

0.00507 0

0 0

0.00577 0

0 0

0.07548 0

0 0

0.04403 0

0 0.0303 0

0 0.46 0.199 0 0

0.15 0

-07 1080400 0.06734 6438 0.4144 0

0 179820 0.10878 0

1065.6 0.481 0 0

31302 0.3069 0

0

-06 0

0 0

ci, 0:

0.

0 02

.0, 1.52 Q.02

'I 0>.03 0;.01 X.

02 0.06

.65 g,.1 0.14 d.o08 0

0 1

0.22 0.22 1 1.48 1 0.35 1

0 0

1 0

0 2

0 0

381.1 0.09 131.35 1228.4 0

0 0

D 0.04 0.13 0.04 0.09 0.26 0

0 0.0D3 0.48 5846 0

0 0

32893 0

0.39 0.61 0.35 0

0 Tel31m 0

0 Te132 NONE 0

,0 NONE Xel33 0

0 NONE INONE 0

0 NONE Xel35 0

0 NONE 4.57B+04 9.'

0 0

4.05E+04 8.27B-05 5.79B+04 9.228-06 0

6.43B+04 2.23E-04 0

5.39B+04 2.86E-05 0

NONE 11310rg 4.31E+03 6.422-0 0

I1320rg 3.972+04 2.51E-06 0

0 0

Ti) i 71 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 Xel31m Xel33m Xe133 I1310rg 11320rg Tel3lm Tel32 end participating isotol Xr87 Kr88 Kr89 Xel35m Xel35 Xe137 11330rg I1340rg Xel38 I1350rg 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 0.01 8.25 8.25 0

8.25 0

0 48 0

0 0

0 endto control volume end_release frac end core CeGrp 0

0 LaGrp 0

0 SrGrp 0

0 controlvolume objitype name air volume water volume surfacearea has recirc filter end control volume controlvolume obitype name airvolume water_ volume surface area has recirc filter endcontrol volume OBJ _CV GAP 100 0

-a f alse OBJ CV RB 100 0

0 false control volume obj. type name air volume water volume.

surfacearea has recirc filter breathing yate Time (hr)

Value 48 0.00035 end breathingrate occupancy factor Time (hr)

Value 48 1

end occupancy factor endcontrol volume junction OBJ CR Control_Room 4.15e+004 0

false (cms)

(frac)

PSAT 3019CF.QA.05 junction type downstream location upstream downstream has filter flow rate Time (hr)

Value (cfm) 48 1

end flow rate endjunction junction junction type do istiea 'Iocatioh-upstream downstream has filter flow rate Time (hr)

Value (cfm) 23.9833 0

24 0.571 48 0

endflowrate filter efficiency Time NobleGas Elemlodine 48 0

0 end filter-efficiency frac 4 daughter resusp Time NobleGas ElemIodine 48 0

0 end frac_4_daughter resusp reevolution rate Time NobleGas ElemIodine 48 0

0 endreevolutionrate endjunction Attacbment A NPIUT.DAT, 24 hr, 0%/6 Rev 0 AIR JUNCTION AIRSPACE CORE GAP false AIR JUNCTION AIR SPACE;;

GAP RE true OrgIodine 0.995 orgIodine 0

OrgIodine 0

PartIodine Solubles o

0 PartIodine Solubles 0

0 PartIodine Solubles 0 -

0 Insolubles 0.99999 Insolubles 0

Insolubles 0

junction junction type downstream location upstream downstream E

hasfilter 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)

AIR JUNCTION AIRSPACE RB environment

!aloe

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 downstream location upstream downstream has filter flow rate Time (hr)

Value (cfm) 48 3700 endflow rate endjunction AIR =IiUNCTION-AIRSPACE environment Control Room false junction junction type downstream location upstream downstream has filter 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 AIR JUNCTION AIR-SPACE Control_Room environment false

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 Xel31m Xel33m Xel33 Xe:

1131Org 1l320rg II:

Tel31m Te132 endjparticipatingisotopes core thermalpower

'iilit mental iodine frac organic iodine -frac particulate iodinefrac release frac to controlvolume GAP Time NGas IGrp CSGrp TeV 0.01 8.25 6.25 0

e.:

48 0

0 0

0 endtocontrolvolume endrelease frac end-core

.7 13 Sm 3

3 rg Kr8B Kr89 Xel35 Xel37 11340rg Xe13 8 113 S0rg 1950

' -. b

..i...

1.0 0.0 3rP 25 BaGrp NM4tls 0

0 0

0 OBJ CV GAP 100 0

CeGrp 0

0 LaGrp 0

0 SrGrp 0

0 control volume obj_type name air volume water volume surfacearea has recirc filter end control volume controlvolume obj_type name air volume water volume surface area has recirc filter endcontrol volume control volume objtype name air volume water volume surfacearea hasrecirc filter 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 false OBJCV RB 100 0

0 false OBJ CR Control Room

4. 15e+004 0

0 false j unction

PSAT 3019CF.QA.05 junction type downstream-location upstream downstream has filter flow rate Time (hr)

Value (cfm) 48 1

end flow rate endjunction junction junction type downstream location upstream downstream has filter flow rate Time (hr) Value (cfm) 23.9633 0

24 0.571 48 0

endflowrate filter_efficiency Time NobleGas Elemlodine 48 0

0 endfilter efficiency frac 4 daughter resusp Time NobleGas Elemlodine 48 0

0 end frac_4 daughterresusp reevolution rate Time NobleGas ElemIodine 48 0

0 end reevolution rate endjunction junction junction-type downstreamlocation upstream downstream hasfilter 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 Attachment A INPUTTDAT, 24 hr, 20%

Rev 0 AIR JUNCTION AIRSPACE CORE GAP false AIR JUNCTION

-* AIRSPACB GAP RB true OrgIodine 0.995 OrgIodine 0

OrgIodine 0

PartIodine 0

Solubles Insolubles 0

0.99999 Solubles Insolubles-0 0

Solubles Insolubles 0

0 AIR_JUNCTION AR_SPACE RB environment false

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 downstream location upstream downstream has filter flow_rate Time (hr)

Value (cfm) 48 3700 end-flowrate endj unction AIRJUNCTION AIRSPACE environment ControlRoom false junction junction type downstreamlocation upstream downstream has filter 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 AIRJUNCTION AIR_SPAQE Control.Room environment false environment breathingratesb Time (hr)

Value 24 0.0 26 0.00035 48 0.0 end breathingrate-sb breathing ratelpz Time (hr)

Value 48 0.0 (cms)

(cms)

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 Kr Xel31m Xel33m Xel33 Xe 11310rg 11320rg Ii Tel31m Tel32 end participating isotopes core thermalpower elemental iodine frac organiciodine frac

-particulate iodine frac release frac to controlvolume GAP Time N Gas I-Grp CsGrp Tel 0.01 8.25 8.2S 0

8.:

120 0

0 0

0 endto controlvolume end release_frac endcore 87 135m 330rg Kr88 IKrB.9 Xel35 Xel37 113 40rg Xe£38 113 50rg 1950 0.0 1.0 0.0

rp 25 BaGrp 0

0 NMtls 0

0 CeGrp 0

0 LaGrp 0

0 SrGrp 0

0 control volume obj type name air volume water volume surface area has recircfilter end control volume control volume obj_type name air volume water volume surface area hasrecirc filter end control volume OBJ CV GAP 100 0

0 false OBJCV RB 100 0

0 false controlvolume obj type name airvolume water volume surface area has recirc filter breathing rate Time (hr)

Value (cms) 120 0.00035 endbreathingrate occupancy factor Time (hri Value (frac) 120 1

endoccupancyfactor end control volume OBJ CR Control_Room 4.15e+004 0

0 false junction

PSAT 3019CF.QA.05 junction type downstream location upstream downstream hasfilter flow rate Time (hr)

Value (cfm) 120 1

end-flow rate endjunction junction junction type Jdownstteamlocation upstream downstream has filter flowrate Time (hr)

Value (cfm) 95.9833 0

96 0.571 120 0

end flow rate filter efficiency Time NobleGas Elemlodine 120 0

0 endfilterefficiency frac_4_daughter resusp Time NobleGas ElemIodine 120 0

0 end frac_4_daughter resusp reevolution rate Time Noble~as ElemIodine 120 0

0 end reevolution rate end_junction Attachment A4 - INPUT.DAT, 96 hr. 0%

Rev 0 AIR JUNCTION AIR SPACE CORE GAP false AIR JUNCTION AIRSPACE

--= -- -

GAP RB true OrgIodine 0.995 OrgIodine 0

OrgIodine 0

PartIodine 0

Solubles 0

Solubles a

Insolubles 0.99999 Insolubles 0

Insolubles 0

junction junction_type downstream location upstream downstream has filter 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)

AIR JUNCTION AIRSPACE RB environment false

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 downstream-location upstream downstream has filter flowrate Time (hr)

Vali 120 3V endflowrate endjunction AIR JUNC N...-

AIRSPACE environment Control Room false le (cfm) 700 junction junction type downstream location upstream downstream has filter 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 AIR JUNCTION AIRSPACE Control Room environment false

PSAT 3019CF.QA.05 junction type downstream location upstream downstream has filter flow rate Time (hr) value (cfm) 120 1

end flow-rate end junction Attachment A INPUT.DAT, 96 hr, 20%

Rev 0 AIR JUNCTION AIRSPACE CORE GAP false junction junction type

--downstxream.4ocation s

upstream downstream has filter fllow_rate Time (hr)

Value (cfm) 95.9833 0

96 0.571 120 0

end flow rate filter_efficiency Time NobleGas ElemIodine 120 0

0 endfilter-efficiency frac 4daughter resusp Time NobleGas Elemlodine 120 0

0 end frac_4_daughter resusp reevolution rate Time Noble as ElemIodine 120 0

0 end reevolution rate endjunction junction junction-type downstream-location upstream downstream hasfilter 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 GAP RB true AIR_JUNCTION OrgIodine 0.995 OrgIodine 0

OrgIodine 0

PartIodine Solubles 0

0 PartIodine 0

PartIodine 0

Solubles 0

Insolubles 0.99999 Insolubles 0

Insolubles 0

AIR JUNCTION AIR_SPACE RB environment false

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 Xel31m Xel33m Xe133 Xe135m

}1310rg 11320rg I1330rg Tel31m Tel32 end participating isotopes Kr88 KrB9 Xel35 Xel37 11340rg Xel38 I1350rg

-:=.

., V~-:

'sT; core thermal_power

.elemental iodine frac organic iodine frac particulate iodine frac release frac to controlvolume GAP Time N Gas I Grp CsGrp 0.01 8.25 8.25 0

120 0

0 0

end to control volume end release frac endcore 1950

_--.z

..5 1.0 0.0 TeGrp 8.25 0

BaGrp 0

0 NMtls 0

0 CeGrp 0

0 LaGrp 0

0 SrGrp 0

0 control volume obj. type name air volume watervolume surface area hasrecirc filter end control volume control volume obj_ type name air volume watervolume surface area has recircfilter endcontrolv olume OBJ CV GAP 100 0

0 false OBJCV RB 100 0

0 false controlvolume obj type name air volume water volume surface area has recirc filter breathing rate Time (hr)

Value 120 0.00(

end breathing rate occupancy factor Time (hr)

Value 120 1

endoccupancy factor end control volume OBJ CR ControlRoom 4.15e+004 0

0 false

(

Icms) 035

! (frac) junction

PSAT 3019CF.Qk05 junctiontype downstream location upstream downstream has filter flow-rate Time (hr)

Value (cfm) 120 1

endflow-rate endjunction junction junction type z::._:downgttrekiulocation...............

upstream downstream has filter flow rate Time (hr)

Value (cfm) 95.9B33 0

96 0.571 120 0

end-flow rate filter-efficiency Time NobleGas Elemlodine 120 0

0 endfilterefficiency frac 4 daughterresusp Time NobleGas Elemlodine 120 0

0 end frac_4 daughter resusp reevolution rate Time NobleGas Elemiodine 120 0

0 enddreevolutionrate endjunction Attachment A NPUT.DAT, 96 hr. 0%

Rev 0 AIR JUNCTION AIR_SPACE CORE GAP false AIR JUNCTION

AIRCSPACE GAP RB true OrgIodine 0.995 OrgIodine 0

OrgIodine 0

PartIodine 0

Solubles 0

Insolubles 0.99999 Insolubles 0

Insolubles 0

junction junctiontype downstreamlocation upstream downstream basfilter 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 Q 3_site boundary X)over_Q_4_lowypopulationzone Time (hr)

Value (s/M*3)

AIR JUNCTION AIRsPACE RB environment false

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 downstreamlocation upstream downstream hasfilter flowrate Time (hr)

Value (cfm) 120 3700 endflow rate endjunction AIR. JUNCTION AIR SPACE environment Control Room false junction junction type downstreamlocation upstream downstream has filter 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 AKR_JUNCTION AIRSPACE Control Room environment false 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 AIR JUNCTION AIR SPACE junction type downstream location upstream downstream has filter flowrate Time (hr)

Value (cfm) 120 1

end flow rate endjunction junction junction type

-.downst-ream.-location.

..--n upstream downstream has filter flow rate Time (hr)

Value (cfm) 95.9833 0

96 0.571 120 0

end flow rate filter efficiency Time NobleGas ElemIodine 120 0

0 end filter efficiency frac_4_daughter resusp Time NobleGas Elemlodine 120 0

0 end frac 4 daughter resusp reevolution rate Time Noblecas Elemlodine 120 0

0 end reevolutionrate endjunction CORE GAP false AIR JUNCTION AIR_ SPACE GAP RB true OrgIodine 0.995 Orgrodine 0

OrgIodine 0

PartIodine 0

Solubles 0

Insolubles 0.99999 Solubles Insolubles 0

0 Solubles Insolubles 0

0 junction junction type downstream location upstream downstream has filter 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 AIRJUNCTION AIRSPACE RB environment false

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 downstream location upstream downstream has filter flow_rate Time (hr)

Value (cfm) 120 3700 end flow rate endjunction junction junctiontype downstream location upstream downstream has filter 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 AIR JUNCTION AIR_SPACE environment Control Room false AIRJUNCTION AIR_SPACE Control Room environment false 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 Xel31m Xel33m Xel33 I1310rg I1320rg Kr87 Xel35m 11330rg

,Kr8B Kr89 Xe135 Xe137 113 4 rg Xel38 I1350rg Tel3lm Tel32 end participating isotopes "I s core thermal_power

.elementaliodinefrac, organiciodine frac particulate iodine frac releasefrac to control volume GAP Time N Gas I Grp CsGrp TeGrp 0.01 8.25 8.25 0 8.25 120 0

0 0

0 endto control volume end release frac endcore 1950 S_

_ 9-..

1.0 0.0

,7~ ';

.y.*,.

.I....

BaGrp 0

0 NMtls 0

0 CeGrp 0

0 LaGrp 0

0 SrGrp 0

0 controlvolume obji type name air volume water volume surface area has recirc filter end control volume control volume obj_ 'type name airvolume water volume surface area has recirc filter endcontrol volume control volume obj_type name airvolume water volume surface area has recirc filter breathingrate Time (hr)

Value (cms) 120 0.00035 end breathingrate occupancyjfactor Time (hr)

Value (frac) 120 1

end occupancy factor end controlvolume OBJCV GAP 100 0

0 f alse OBJ CV RB 100 0

0 f alse OBJ CR Control Room 4.15e+0O04 0

b false junction

PSAT 3019CF.QA.05 end breathing rate lpz end environment Attachment A INPUTDAT, 96 hr, 200%

Rev 0

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*~'.~;

' *At S96.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 511 l (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 Form QA-007 Document TransmittallRecelpt

..;- '. "7-

-I -, T Pedro Perez Vermont Yankee Date: 6/24/03 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

Return to:

Julie Loya Polestar Applied Technology, Inc.

One First Street Suite 4 Los Altos, CA 94022 Date:

_/_ __3 N

I

QAP 6. 1 Revision 0 4/28/95 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

Text

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