View source for NL-13-115, Indian Point, Unit 2 - IP-CALC-11-00091 AST Analysis of IP2 to Address the Impact of Containment Sump Solution Bazk-Leakage to the RWST After LOCA

{{Adams
| number = ML17104A042
| issue date = 11/16/2011
| title = Indian Point, Unit 2 - IP-CALC-11-00091 AST Analysis of IP2 to Address the Impact of Containment Sump Solution Bazk-Leakage to the RWST After LOCA
| author name = Golshani M
| author affiliation = Entergy Nuclear Operations, Inc
| addressee name = 
| addressee affiliation = NRC/NRR
| docket = 05000247
| license number = DPR-026
| contact person = 
| case reference number = NL-13-115, NL-17-035, TAC MF1440
| document report number = IP-CALC-11-00091, Rev. 0
| package number = ML17104A039
| document type = Calculation
| page count = 39
| project = TAC:MF1440
| stage = Other
}}

=Text=
{{#Wiki_filter:ENCLOSURE 1 TO NL-13-115 INDIAN POINT CALCULATION IP-CALC-11-00091 AST ANALYSIS OF IP2 TO ADDRESS THE IMPACT OF CONTAINMENT SUMP SOLUTION BACK-LEAKAGE TO THE RWST AFTER LOCA ENTERGY NUCLEAR OPERATIONS, INC. INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247  

CALCULATION CONTINUATION SHEET SHEET No.1 of 33 CALC *. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA . CALC. NO.: IP-CALC-11-00091 REVISION NO. 0 A'l'TACRME'N'l' 9
* 2 ENGINEElt:ING CALctJLATION COVER PAGE Sheet 1 of 1 I ' D AN0-1 D AN0-2 D GGNS
* IP-2 D IP-J 0 JM D PNPS 0 RBS D VY D W3 CALCULATION (l.J EC # 32007 121 Page 1 Of 33 COVER PAGE (3) (4) r Design Basis Cale.
* YES o*No
* CALCULATION 0 EC Markup I Calculation No: IP-CALC-11-00091 (6) Revision:
I (7) Title: AST of XP2 to Address the Xmpact of "" Edito:r;ial Containment Sump Solution Back-Leakage to the RWST after LOCA 0 YES
* NO (9) System(s):
RWST (10) Review Org (Department):
FNA 0 (11) Safety Class: < 121 Component 
/Equipment I Structure 
'l'ype/Number:
* Safety I Quality Related D Augmented Quality Program D Non-Safety Related : (13) Docwnent Type: CALCULATION 14> Keywords (Description/Topical codes): RADTRAD 3.03 REVIEWS 1151 Name/Signature/Date 
<161 (17) Name/Signature/Date 
'/ 15:.**
A. Irani * * \I /1.<. 'JI Respoui1bie Engineer Design verifier D Reviewer ll/16' JI Comments Attached D Comments, Attached l
CALCULATION CONTINUATION SHEET I SHEET No.2 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 I REVISION NO. I 0 ATTACHMENT 
: 9. 3 CALCULA'r!ON REFERENCE SHEET Sheet 1 of 1 CALCULATION REFERENCE CALCULATION NO: IP-CALC-11-00091 SHEET REVISION:
0 I. EC Markups Incorporated 
: 1. None. II. Sht Rev Input Output Impact Tracking Relationships:
Doc Doc Y/N No. CN-CRA-03-55 
-0
* D N N/A PU2-E-03-20 
--* D N N/A CN-CRA-11-25 
-0
* o* N N/A PU2-E-03-20 
--* D N N/A CN-REA-03-4 
--* D N N/A IP-RPT-11-00025 
-0
* D N N/A NEA-00023 
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* D N N/A IP-CALC-11-00063 
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* D N N/A III. CROSS 

==REFERENCES:==

.. 1. RG 1.183 2. NUREG/CR-5950 
: 3. *MUREG/CR-6604 IV. SOF'l'WARE USED: Yes, See Method.of Analysis Title: RADTRAD , Version/Release:
3.03 Disk/CD No. v. DISK/CDS INCLUDED:
None Title: Version/Release Disk/CD No. VI. OTHER CHANGES: None  
-:::::::-Entergy ATTACHMENT 
: 9. 4 Sheet 1 of 1 CALCULATION CONTINUATION SHEET SHEET No.3 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 REVISION 0 RECORD OF REVISION Initial issue. 0  
-===-Entergy CALCULATION CONTINUATION SHEET SHEET No.4 of 33 CALC. TITLE: AST Analysis qf IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 REVISION NO. 0 TABLE OF CONTENTS Section Calculation Cover Page Calculation Reference Sheet ......................... . Record of Revision Table of Contents 1. Purpose and 
: 2. Summary of Results & Conclusion 
............... . 3. Design Inputs ................................. . 4. 5. Acceptance Criteria Method of Analysis 6. Calculation/Analysis 
.......................... . 7. 8. 6. 1 Fission Product Inventory 
.. -............... . 6.2 Iodine Partition Factor in the RWST ....... . 6.3 Determination of Elemental Iodine Fractions based on RWST pH Results References Attachment A Attachment B Attachment C Sheet No. 1 2 3 4 5 6 9 10 11 12 12 17 23 32 33 3 Pages 1 Page 10 Pages  
*-Entergy CALCULATION CONTINUATION SHEET SHEET No.5 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 REVISION NO. 0 1.0 Purpose and Background The radiological dose consequences of a large break Loss-Of-Coolant Accident (LOCA) provided by Westinghouse in Reference 1 for Indian Point Unit 2 (IP2} did not include the dose contribution resulting from the postulated back-leakage of containment sump water to the Refueling Water Storage Tank (RWST). The dose from this leakage was considered to be negligible.
This calculation is being performed to quantify the allowable sump back-leakage to the RWST and evaluate the doses at IP2 Control .Room (CR) and offsite in the event of a design basis LOCA. Two allowable back-leakage flow rates were considered: 
: 1) An allowable back-leakage which does not result in an increase in the dose specified in the FSAR (Sec. 14.3.6.8).
This is able to be accomplished by using up the additional conservatism that was included in the FSAR values. 2) An allowable back-leakage which does not result in an increase in the dose acceptance limit of 10 CFRS0.67 (e.g., 5 rem CR TEDE). The analysis is performed based on the Alternative Source Term I . (AST) methodology described in Reg. puide 1.183 (Ref. 2) and using the RADTRAD 3.03 computer code (Ref. 3).
CALCULATION CONTINUATION SHEET I SHEET No.6 of 33 -CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 I REVISION NO. I 0 2.0 Summary of Results & Conclusion The IP2 doses resulting from the back-leakage to the RWST in the IP2 Control Room (CR), Exclusion Area Boundary (EAB) and Low Population Zone (LPZ) were calculated in the event of a design basis LOCA. The CR doses were calculated for allowable back-leakage to remain below the CR dose reported in the FSAR and to calculate allowable back-leakage value for less than the lOCFRS0.67 limit of 5 rem CR TEDE. Tables 2.1 and 2.2 show the summary of results. The results of analysis in Table 2.1 indicate that the EAB, LPZ and CR doses are less than reported in the FSAR for the back-leakage flow rate of 20 gph. The results of the analysis in Table 2.2 for 29 gph flow rate are also indicated that doses are below the 10 CFR 50.67 limit of 5 rem CR TEDE.  

CALCULATION CONTINUATION SHEET SHEET No.7 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 REVISION NO. 0 Table 2.1 IP2 LOCA '?EDE Doses (rem) [20 gph Back-Leakage) c a s e Back-Leakage To RWST Calculated Containment 
& ECCS leakage (Ref. 1)
* Total Reported Dose (Refs. 1 & FSAR) '?EDE Limit CR EAB LPZ 0.1701 0.09263 4.7263 16.91 12.93 4.896 16.91 13.02 4.9 17.8 13.6 5.0 25.0 25.0
* An additional external dose to the CR is also included.  

CALCULATION CONTINUATION SHEET SHEET No.8 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 REVISION NO. 0 Tabl.e 2.2 IP2 LOCA TEDE Doses (rem) [29 gph Back-Leakage) c a s e CR BAB --Back-Leakage 0.2655 0.1481 To RWST Calculated Containment 
& ECCS leakage (Ref. 1 )
* 4.7263 16.91 12.93 Total 4.99 16.91 13.08 TEDE Limit 5.0 25.0 25.0
* An additional external dose to the CR is also included.  

CALCULATION CONTINUATION SHEET SHEET No.9 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impkct of Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 REVISION NO. 0 3. Design rnputs Design Input Data Parameter Plant Power Core Inventories Release Fraction & Timing Chemical Form Release to Containment
_Value 3,280.3* MWt Table 6.1 Table 6.2 (R.G. 1.189) Sec. 6.1 (R.G. 1.189) See Attachment -C for all other design input data.
* Core power of 3216 MWt with a reactor power uncertainty of 2%  

CALCULATION CONTINUATION SHEET SHEET No.10 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 REVISION NO. 0 4. Acceptance Criteria The radiological criteria for the CR, EAB and LPZ are in 10 CFR 50.67 and Reg. Guide 1.183. CR Dose Acceptance Criterion:
EAB Dose Acceptance' Criterion:
LPZ Dose Acceptance Criterion:
5.0 rem TEDE 25.0 rem TEDE 25.0 rem TEDE  
-Entergy CALCULATION CONTINUATION SHEET SHEET No.11 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 REVISION NO. I 0 5. Method of Ana1ysis Post-accident LOCA radiation exposures from the postulated leakage of containment sump water to the RWST in the IP2 CR, EAB and LPZ were computed using the following: (a) The methodology and assumptions in Regulatory Guide 1.183 (Ref. 2), (b) Appropriate source terms, release pathways, and other assumptions, .as described in the section which follows, (c} Post-accident atmospheiic dispersion factors, and (d) The following Computer Code: RADTRAD 3.03 (Ref. 3) The NRC sponsored code RADTRAD, Version 3.03 was used to model the DB LOCA and estimate the dose consequences.
The CR, EAB and LPZ doses in terms of TEDE were calculated for the LOCA. Section 6 and Attachment C present details of the assumptions, data and results associated with the accident analyzed.  
*--Entergy CALCULATION CONTINUATION SHEET SHEET No.12 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 REVISION NO. 0 6. Calculation/Analysis Release pathways and contributing radiation sources, which should be I analyzed in the design-basis LOCA, are the followings: 
(1) Containment leakage, (2) ECCS recirculation leakage, (3) External dose cloud, and (4) Back-leakage of sump water to the RWST. Doses resulting from activity released through the first three pathways were calculated in Reference 
: 1. The last release pathway was not addressed in previous dose analyses for IP2 (Reference 1). Therefore, this calculation is being performed to evaluate the doses at IP2 Control Room {CR) and offsite from the back-leakage to the RWST in the event of a design basis LOCA. The source term and basic assumptions for evaluating the TEDE dose associated with a postulated back-leakage to the RWST during the design-basis LOCA were selected to be consistent with Regulatory Guide 1.183 (Ref. 2). 6.1 Fission Product Inventory The fission product inventory in the core is based on full power operation (3216 MWt + 2% uncertainty, i.e., 3280.3 MWt). The core inventory of radionuclides of interest is shown in Table 6.1 from Ref. 5. The reactor core inventory release fractions, for each radionuclide group and for the gap release and early in-vessel I I I _________
_J  
' ,
CALCULATION CONTINUATION SHEET SHEET No.13 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 REVISION NO. 0 damage phases for the OBA LOCA are shown in Table 6.2 (Ref. 2). The chemical form of the radionuclide released to the containment should be assumed to be 95% cesium iodine, 4.85% elemental iodine and 0.15% organic iodine (Reg. Guide 1.183). Since the 0.15% of the iodine released from the core is assumed to be in the organic form and thus is not subject to removal by sprays or deposition and would remain the containment air space. Therefore, the corrected fraction of 0.05 and 0.35 for halog*ns from Table 2 of Reg. Guide 1.183 should be adjusted to 0.05 x (1-0.0015) 
= 0.049925 and 0.35 x (1-0.0015) 
= 0.349475 in RADTRAD input file. The iodine release fraction is also specified as 97% elemental and 3% organic from Reg. Guide 1.183 when iodine is released from liquid. The release fractions for all other nuclide groups are set at zero since they are not subject to release by the containment sump back-leakage pathway to the RWST.  

CALCULATION CONTINUATION SHEET SHEET No.14 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA Nuclide Halogens I 130 I 131 I 132 I 133 :r 134 :r 135 CALC. NO.: IP-CALC-11-00091 REVISION NO. 0 Table 6.1 Core Inventories of Nuclides for use in Radiological Design-Basis Applications Activity Nuclide Activity (Ci) Alkal.i (Ci/MWt) 3.80E+06 Cs134 2.06E+07 9.16E+07 Cs136 6.01E+06 l.33E+08 Cs 137 1.19E+07 l.88E+08 Cs138 1.71E+08 2.06E+08 Rb86 2.38E+05 1.75E+08 Tellw::ium Te 127 9.84E+06 Te 127m l.29E+06 Te 129 2.92E+07 Te 129m 4.30E+06 Te 13lm l.33E+07 Noble Gases Te 132 l.31E+08 Sb 127 9.95E+06 Kr 83m 2.93E+03 Sb 129 2. 97E+07-Kr 8Sm 2.43E+07 Kr 85 1.10E+06 Ba, Sr Kr 87 4.66E+07 Kr 88 6.56E+07 Ba 139 1.67E+08 Ba 140 1.61E+08 Xe 131m 1. 01E+06 Sr 89 8.83E+07 Xe 133m 5.87E+06 Sr 90 8.75E+06 Xe 133 1. 80E+08 Sr 91 l.11E+08 Xe 13Sm 3.68E+07 Sr 92 1.20E+08 Xe 135 4.77E+07 Xe 138 1. 55E+08 CALCULATION CONTINUATION SHEET I SHEET No.15 of 33 *Entergy CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA Nuclide Noble Metals Ru 103 Ru 105 Ru 106 Rh 105 Mo 99 Tc 99m Lanthani.des La 140 La 141 La 142 Zr 95 Zr_ 97 Nd 147 Nb 95 y 90 y 91 y 92 y 93 Cm 242 Cm 244 Pr 143 Am 241 CALC. NO.: IP-CALC-11-00091 I REVISION NO. Table 6.1 Core Inventories*
of Nuclides for use in Radiological Design-Basis Applications Activity Nuclide Activity (Ci/MWt) Cerium (Ci/MWt) 1. 40E+08 Ce 141 1.52E+08 9. 62E+'07 Ce 143 1.42E+08 4.89E+07 Ce 144 1.20E+08 -8. 86E+07 Pu 238 4.13E+05 1.75E+08 Pu 239 3.50E+04 1.53E+"08 Pu 240 S.23E+04 Pu 241 1.18E+07 Np 239 1.88E+09 1. 73E+08 1.53E+08 1.48E+08 1.54E+08 1.SSE+OB 6.11E+07 1.56E+08 9.11E+06 1.14E+08 1.20E+08 1.39E+08 3.52E+06 3.82E+OS 1.37E+08 1.41E+04 I 0  
--=--Entergy CALCULATION CONTINUATION SHEET SHEET No.16 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 REVISION NO. 0 Table 6.2 Core Inventory Fraction Released into Containment Release (Table 2 of Regulatory Guide 1.183) Group Gap Release 1 Early In-Vesse1 2 Total Noble Gases 0.05 0.95 1.0 Halogens 0.05 0.35 0.4 A1kali Metals 0.05 0.25 0.3 Tellurium Metals 0.00 0.05 0.05 Ba, Sr 0.00 0.02 0.02 Noble Metals 0.00 0.0025 0.0025 Cerium Group 0.00 0.0005 0.0005 Lanthanides 0.00 0.0002 0.0002 Note: (Ref. 1) 1. Gap release in 30 seconds and 0.5 hr duration 2. Early In-Vessel release in 0.5 hr and 1.3 hr duration  
--Entergy CALCULATION CONTINUATION SHEET SHEET No.17 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 REVISION NO. I 0 6.2 Iodine Partiti.on Factor in the RWST Two flow rates (20 and 29 gal/hr) to the RWST were selected:
one for an allowable back-leakage which does not result in an increase in the dose specified in the FSAR (Table 12.1) and the second one, an allowable back-leakage which does not result in an increase in the dose acceptance limit of 10 CFR50.67 (5 rem CR TEDE). (In order to find these two flow rates a few flow rates were assumed and run RADTRAD.)
The potential leak path of the sump solution to the RWST is from the Emergency Core Cooling System (ECCS) pump(s) to the RWST water by the way of the piping volume. This is modeled by the transfer of a portion of the flow going to the RWST air and a portion to the RWST water in order to meet the iodine partition factor. The following Equation from Section 3.3.l of NUREG/CR-5950 (Ref. 6) was used for equilibrium partition coefficient:
0.0149T (Where T temperature in K) Using the maximum RWST solution temperature of 114&deg;F (318.71 K) during a 30 day accident period from the input data, the equilibrium partition coefficient was calculated to be 34.77. This factor is defined in terms of concentration, not in terms of activity.
Because of the RWST volumes of 13,900 gallons in the liquid space and 38,6000 gallons in the air space, there is a factor of 386000/13900 27.77 adjustment that needs taken into account to convert the partition coefficient to a volume basis:  

CALCULATION CONTINUATION SHEET SHEET No.18 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 REVISION NO. 0 34.77/27.77 
= 1.25. Therefore, if x = gpm to the RWST liquid space and y RWST air space, then x + y 0.33333 x I y = 1. 25 x + y x I y 0.48334 1.25 For 20 gph or 0.16667 gpm For 29 gph or 0.33333 gpm Where y and x are calculated to be: gpm to the Y= 0.14815 gpm and x 0.18518 gpm for flow rate of 20 gph Y= 0.21482 gpm and x 0.26852 gpm for flow rate of 29 gph However, the volume of liquid and air will be changing with time (starting at 6.5 hrs 20 or 29 gallons per hour will be added to the RWST water volume and subtracted from the air volume). As a result, the partition factor.will also change with time. Tables 6.3 and 6.4 below from the spread sheet show the results for 20 and 29 gph.
CALCULATION CONTINUATION SHEET SHEET No.19 of 33 CALC. TITLE: AST Analysis of IP2 to Address the -::::=--Entergy Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 REVISION NO. 0 Table 6.3 Flow to the RWST (20 gph) Flow Eq. Par. rate 20 coef 34.77 Time RWST Ratio of Flow to Flow to Flow to Flow to RWSTAIR water air Partition air water air water Volume volume (hr} (gal} (gal) to water Factor (gal/min) (gal/min} (cfm) (cfm) 6.5 386000 13900 27.7698 1.25 0.14801 0.18532 0.01979 0.02478 75 384630 15270 25.1886 1.38 0.14003 0.19330 0.01872 0.02584 100 384130 15770 24.3583 1.43 0.13732 0.19601 0.01836 0.02621 150 383130 16770 22.8462 1.52 0.13217 0.20116 0.01767 0.02689 200 382130 17770 21.5042 1.62 0.12738 0.20596 0.01703 0.02754 300 380130 19770 19.2276 1.81 0.11869 0.21464 0.01587 0.02870 400 378130 21770 17.3693 2.00 0.11104 0.22229 0.01485 0.02972 500 376130 23770 15.8237 2.20 0.10425 0.22908 0.01394 0.03063 600 374130 25770 14.5180 2.39 0.09819 0.23515 0.03144 720 371730 28170 13.1960 2.63 0.09170 0.24163 0.01226 0.03231 Table 6.4 Flow to the RWST (29 gph) Flow 29 Eq. Par. 34.77 rate Coef RWST Ratio of Flow to Flow to Flow to Flow to Time RWSTAIR water air Partition air water air water Volume volume (hr) (gal) (gal) to water Factor (gal/min) (gal/min) (cfm) (cfrn) 6.5 386000 13900 27.7698 1.25 0.21462 0.26872 0.02869 0.03593 60 384448.5 15451.5 24.8810 1.40 0.20160 0.28173 0.02695 0.03767 75 384448.5 15886.5 24.1997 1.44 0.19835 0.28499 0.02652 0.03810 100 383288.5 16611.5 23.0737 1.51 0.19280 0.29053 0.02578 0.03884 150 381838.5 18061.5 21.1410 1.64 0.18276 0.30058 0.02443 0.04019 200 380388.5 19511.5 19.4956 1.78 0.17364 0.30969 0.02322 0.04141 300 377488.5 22411.5 16.8435 2.06 0.15773 0.32560 0.02109 0.04353 400 374588.5 25311.5 14.7991 2.35 0.14430 0.33903 0.01929. 0.04533 500 371688.5 28211.5 13.1751 2.64 0.13282 0.35052 0.01776 0.04686 600 368788.5 31111.5 11.8538 2.93 0.12288 0.36045 0.01643 0.04819 720 365308.5 34591.5 10.5606 3.29 0.11260 0.37073 0.01505 0.04957  
-===-Entergy CALCULATION CONTINUATION SHEET SHEET No.20 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of. Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 REVISION NO. 0 There is no transport of activity into the RWST was assumed to occur until 81.5 hours for 20 gph and 66.5 for 29 gph after accident due to delay of 6.5 hours to initiate back-leakage and 75 hours or 60 hours delay imposed by the piping volume from input data [1750 gal (see page 2 of input data)/20; 87.5
* 75 hours and 1750/29 = 60.3
* 60]. For the 81.5 hrs time step, the determined at 75 hours and for the 66.5 hrs time step, flows determined at 60 hours can be used since the impact of the additional 

===6.5 hours===
are not significant. " A transfer from the RWST liquid space to the RWST air space should be used, in order to maintain the .partition factors that are calculated above due to the release of activity from the RWST air to the environment.
For 20 gph flow rate, the flowing transfers from the RWST water to the RWST air as a function of time were selected:
Time (hr) 8.15E+Ol 3.SOE+02 5.00E+02 6.50E+02 Flow(gal/min) 0.09 0.2 0.15 0.30 These leakages must be shown to be close agreement with the values calculated in the Table 6.3 by running RADTRAD. See Table below from RADTRAD output of IP2RWST20.00  
-===-Entergy CALCULATION CONTINUATION SHEET SHEET No.21 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump'Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 REVISION NO. 0 Time RWST gas space RWST liquid Effective Partition fac. (hr) I-131 inventory I-131 inventory Partition factor From Table 6. 4 (Ci) (Ci) (col. 3/col. 2) 100 2.2269E+02 3.1674E+02 
: 1. 42 1. 43 300 8.4169E+02 l.5220E+03 
: 1. 81 1. 81 400 7.7482E+02 l.5584E+03 2.01 2.00 500 6.6138E+02 1.4110E+03 2.13 2.20 600 4.7272E+02 l.1368E+03 2.40 2.39 720 2.8779E+02 7.5745E+02 2.63 2. 63 For 29 gph flow rate, the flowing transfers from the RWST water to the RWST air as a function of time were selected:
Time(hr) 8.15E+Ol 3.50E+02 Flow(gal/rnin) 0.09 0.15 These leakages must be shown to be close agreement with the values calculated in the Table 6.4 by running RADTRAD. See Table below from RADTRAD output of IP2RWST29.00 CALCULATION CONTINUATION SHEET I SHEET No.22 of 33 CALC. TITLE: AST Analysis of IP2 to Address the -
Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.; IP-CALC-11-00091 I REVISION NO. I 0 Time RWST gas space RWST liquid Effective Partition fac. (hr} I-131 inventory I-131 inventory Partition factor From Table 6. 4 (Ci) (Ci) (col. 3/col. 2) 75 2.4210E+02 3.4459E+02 
: 1. 42 1. 44 100 5.7103E+02 8.5178E+02 
: 1. 49 1. 51 300 1.3154E+03 2.5391E+03 
: 1. 93 1. 81 400 1.1355E+03 2.5524E+03 2.25 2.06 500 9.1766E+02 2.3094E+03 2.52 2. 64 600 6.4718E+02 1.8015E+03 2.78 2.93 720 3.6115E+02 1.2190E+03 3.37 3.29 The minimum and maximum Tech Spec temperature range for the RWST is 40&deg;F to 110&deg;F (see the input data), but the tank would not have the potential of seeing this kind of temperature swing on a daily basis. A maximum temperature swing of 40&deg;F is used, which is equivalent to having the tank reach 110&deg;F in the day and then drop to 70&deg;F during the night (using high end of the temperature range (i.e., 70&deg;F to 110&deg;F). The flow rate would be calculated from the following Equation.
Where, P1 = P2r v1 is 386000 gal x 0.1337 are 529.67&deg;R and 569.67&deg;R.
51600 ft 3 and T 1 and* Tz Therefore, the volume charige can be determined to be:  

CALCULATION CONTINUATION SHEET SHEET No.23 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 REVISION NO. 0 If the low end of the temperature range is used (i.e., 40&deg;F to 80&deg;F), the volume change can be determined to be: (51600 ft 3) (539. 67&deg;R) I (499. 67&deg;R)-51600 4131 ft 3 The average flow rate over a full day (higher number is conservative) would be 4131/60x24 
= 2.869 cfm. Therefore, 2.9 cfm was used in RADTRAD. 6.3 Detexmi.nation of E1emental Iodine Fractions based on RWST pH Both plants IP2 and IP3 have the same rated thermal power and the source inventory of the core is almost the same. Therefore the amount of iodine source in the core for both plants IP2 and IP3 should be almost the same. Therefore, the iodine inventory in the core of 26121g from Reference 7 was used in this calculation.
The mass of iodine in the sump water would be 26121 g x 0.40 (40% of iodine released from the core, Reg. Guide 1.183) = 10,448 g Iodine concentration in the sump water= 10,448/374000 gal= 2.79E-2 g/gal = 7.37E-3 g/L. The minimum sodium tetraborate decahydrate (Na2B407-lOH20) is 8096 lb (TS 3.6.7.lb).
Sodium tetraborate in solution reverts to a combination of boric acid and sodium hydroxide (NaOH) . The equivalent mass of NaOH is found by taking in the fraction of the CALCULATION CONTINUATION SHEET SHEET No.24 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 REVISION NO. 0 mciss that would exist as NaOH. The molecular weight of NaOH is 39.998 and the molecular weight for sodium tetraborate decahydrate (Na2B407-lOH20) is 381.38. Thus, the effective mass of NaOH is: (8096 lb)x(39.998)/{381.38) 
= 849.1 lb 3.85E+05 grams Taking the mass of NaOH and dividing by the sump volume gives the concentration of NaOH in the sump: 3.85E05 g NaOH /374000 GAL =l.0294 g NaOH/gal (1.0294 g/gal)/(3.7854 l/gal) = 0.2719 g/l The Tech Spec limit for the boron concentration in the RWST and the accumulators is 2600 ppm (TS 3.5.4.3).
Thus, it is conservative to assume that the containment sump solution would also have a boron concentration of 2600 ppm. Using the data from Reference 7 for 2500 ppm boron and 3000ppm boron, the initial RWST pH is between 4.57 and 4.62 (Reference 7). Two RADTRAD cases were run for each flow rate (20 and 29 gph). One for iodine concentration and the other for NaOH concentration (The only changes made to the source term input .nif 1 and .rft 2). Tables below show the iodine concentration lsee RADTRAD output iodineip220.
o0 for 20 gph and conc-iodineip229.o0 for 29 gph) and 1 The .nif files (conc-iodineip2.nif for iodine concentration and naohip2.nif for NaOH concentration) are revised to set the inventory iodine or the mass NaOH. 2 The .rft (loca-i.rft for iodine concentration and con-naohip2.rft for NaOH concentration) are revised to set the 40% inventory for iodine and all of the NaOH needs to be modeled as going to the sump.  
,,.. CALCULATION CONTINUATION SHEET I SHEET No.25 of 33 flt Entergy CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage 
' , to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 I REVISION NO. I 0 the NaOH concentration in the RWST water (see RADTRAD output naohip220.
o0 for 20 gph and' conc-naohip229.o0 for 29 gph).  
--Entergy CALCULATION CONTINUATION SHEET SHEET No.26 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA * ** + CALC. NO.: IP-CALC-11-00091 REVISION NO. 0 Table 6.5 Iodine Concentration in RWST 20 gph F1ow Rate Iodine Concentration Iodine Iodine* Water (g/L)"* Concentration\ (gram) (gal) (g-atoms/Lt
* 350 1.3878E+02 20770 1.765E-03 1.37E-05 400 1.6602E+02 21770 2.015E-03 1.56E-05 450 1.9329E+02 22770 2.243E-03 1.74E-05 500 2.2054E+02 23770 2.451E-03 1.90E-05 550 2.4776E+02 24770 2.642E-03 2.05E-05 600 2.7493E+02 25770 2.818E-03 2.18E-05 650 3.0204E+02 26770 2.98.1E-03 2.31E-05 720 3.3988E+02 28170 3.187E-03 2.47E-05 29 gph F1ow Rate Iodine Iodine Time Iodine'++
Water Concentration Concentration (hr) (gram) (gal) (g/L)** (g-atoms/L) 
+ 350 2.1945E+02 23861.5 2.430E-03 1.88E-05 400 2.6082E+02 25311.5 2.722E-03 2.11E-05 450 3.0104E+02 26761.5 2.972E-03 2.30E-05 500 3.4064E+02 28211.5 3.190E-03 2.47E-05 550 3.7988E+02 29661.5 3.383E-03 2.62E-05 600 4.1886E+02 31111.5 3.557E-03 2.76E-05 650 4.5765E+02 32561.5 3.713E-03 2.88E-05 720 5.1167E+02 34591.5 3.908E-03, 3.03E-05 From RADTRAD computer output: con-iodineip220.o0 (col.2/col.3)/(3.7854 l/gal) The concentration is converted to gram-atoms of I-129 (more than \. 75% of iodine inventory is from I-129) by dividing the concentration (col. 4) by 129 (I-129) ++ From RADTRAD computer output: con-Idineip229.o0  
--===-Entergy CALCULATION CONTINUATION SHEET SHEET No.27 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 REVISION NO. 0 Tab1e 6.6 NaOH Concentration in RWST 20 gph F1ow Rate Time (hr) NaOH water (gal) NaOH (gram) Concentration (g/L( 350 5.1214E+03 20770 6.514E-02 400 6.1266E+03 
.21770 7.435E-02 450 7.1328E+03 22770 8.276E-02 500 8.1387E+03 23770 9.045E-02 550 9.1432E+03 24770 9.752E-02 600 1.0146E+04 25770 1.040E-01 650 1.1146E+04 26770 1.100E-01 720 1.2543E+04 28170 29 gph F1ow Rate Time* (hr) NaOH+ Water( gal) NaOH (gram) Concentration (g/L)"* 350 8.0983E+03 23861.5 8.966E-02 400 9.6250E+03 25311.5 1.005E-01 450 1.1109E+04 26761.5 1.097E-01 500 1.2571E+04 28211.5 1.177E-01 550 1.4019E+04 29661.5 1.249E-01 600 1.5457E+04 31111.5 1.313E-01 650 1.6889E+04 32561.5 1.370E-01 720 1.8882E+04 34591.5 1.442E-01
* From RADTRAD computer output: con-naohip220.o0 
** (col.2/col.3)/(3.7854 l/gal) + From RADTRAD computer output: con-naohip229.o0  
--Entergy CALCULATION CONTINUATION SHEET SHEET No.28 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 REVISION NO. 0 For determining the pH at low NaOH concentration, Reference 7 used the titration curves for trisodium phosphate (TSP) instead. NaOH is a stronger caustic than TSP and the TSP curves thus provides conservatively low estimates of the pH for the NaOH solution.
A pH of 7.75 shown for 1.0 g/L of NaOH in 2500 ppm boron solution in Reference 7 vs. -of a pH of 7.2 for 1.0 g/L of TSP at the same boron concentration from Reference 
: 8. A table below from Table 3 of Reference 8 shows the TSP concentration as function of pH base on 3000 ppm boron solution (Table 3 is attached to Ref. 7). TSP Cone. (g/L) Solution pH 0 4.57 0.025846852 5.62 0.038731624 5.73 0.051590729 5.83 0.064424244 5.91 0.077232245 5.98 0.082348318 6.00 0.092568274 6.05 0.102772008 6.10 0.115503922 6.16 0.128210624 6.19 0.253907314 6.47  
-Entergy CALCULATION CONTINUATION SHEET SHEET No.29 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 REVISION NO. , 0 Therefore the pH at a given RWST NaOH concentration is found by linear interpolating between the above values, as appropriate.
Tables below show the RWST water pH as a function of time.  

Time (hr) 350 400 450 500 550 600 650 .720 Time (hr) 350 400 450 500 550 600 650 720 CALCULATION CONTINUATION SHEET I SHEET No.30 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 Tab1e 6.7 RWST Water pH vs. Time 20 gph F1ow Rate RWST Water pH Na OH Cone. Interpolation (g/L) Range 6.514E-02 5.91 -5.98 7.4359E-02 5.91 -5.98 8.276E-02 6.00 -6.05 9.045E-02 6.00 -6.05 9.752E-02 6.05 -6.10 1.040E-01 6.10 -6.16 1.lOOE-01 6.10 -6.16 l.176E-01 6.16 -6.19 29 gph F1ow Rate RWST Water pH NaOH Cone. Interpolation (g/L) Range 8.966&#xa3;-02 6.00 -6.05 1.005E-01 5.10 -6.05 l.097E-01 6.10 -6.16 1.177E-01 6.16 -6.19 1.249E-01 6.16 -6.19 1.313E-01 6.19 -6.47 l.370E-01 6.19 -6.47 1. 442E-01 6.19 -6.47 I REVISION NO. I 0 RWST Water pH "" 5.92 5.96 6.01 6.04 6.08 6.11 6.14 6.17 RWST Water pH ... 6.03 6.10 6.15 6.17 6.18 6. 21 6.23 6.25 CALCULATION CONTINUATION SHEET I SHEET No.31 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage 
--Entergy to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 I REVISION NO. I 0 Figure 3.1 of Reference 6 (NUREG/CR-5950) was used to determine the amount of iodine converting to the elemental form based on solution pH and iodine concentration.
At a pH of 5.2 and a concentration of 10-5 , the fraction of iodine {1 2) as elemental iodine is about 0.02. As shown in above Table, the RWST pH increases to approximately 6.04 at 500 hours at which point the iodine concentration is 5 g-atom/L for 20 gph flow rate. For 29 gph flow rate, the RWST pH increases to approximately 6.19 at 500 hours at which point the iodine concentration is 2.5E-5 g-atom/L.
Until the pH reaches 6, the fraction of the iodine converting to the elemental form will be assumed to be based on a pH of 5.2 (a conservative assumption).
From Figure 3.1 of NUREG/CR-5950 (Reference 
: 6) and considering the iodine concentration above, this fraction is conservatively selected to be 2% for both flow rates. After 500 hours, the RWST liquid pH will exceed 5.8 and the indicated conversion to elemental iodine is essentially zero for the iodine concentrations calculated above. The fraction converting to elemental form after 500 hours is conservatively assumed to be 0.5% for both flow rates.
Entergy 1. Resu1ts CALCULATION CONTINUATION SHEET I SHEET No.32 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 I REVISION NO. I 0 The offsite and CR doses were evaluated due to dose contribution resulting from postulated back-leakage of containment sump water to the Refueling Water Storage Tank (RWST) . Combining the doses I resulting from the activity that calculated in Reference 1 from the containment leakage and the ECCS leakage give total offsite and CR doses. The doses were calculated; 
: 1) An allowable back-leakage which does not result in an increase in the dose specified in the FSAR (Table 12.1). 2) An allowable back-leakage which does not result in an increase in the dose acceptance limit of 10 CFRS0.67 (5 rem CR TEDE}. There is no EAB dose indicated for the back-leakage to the RWST because back-leakage would not occur until after the identified worst 2-hour interval.
Tables 2.1 and 2.2 present the TEDE in the CR, EAB and LPZ. Refer to Sec. 2 for a summary of the exposures.
It should be noted that the TSC dose was also calculated for information only and the results are in Attachment B.  

===8.0 References===

CALCULATION CONTINUATION SHEET No.33 of 33 CALC. TITLE: AST Analysis of IP2 to Address the Impact of Containment Sump Solution Back-Leakage to the RWST after LOCA CALC. NO.: IP-CALC-11-00091 REVISION NO. 0 1. CN-CRA-03-55, "Indian Point 2 -LOCA Doses for Stretch Power Uprate Program," Revision 0, (10/31/03) 
: 2. US NRC Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors", (July 2000) 3. NUREG/CR-6604, RADTRAD, "A Simplified Model for Radionuclide Transport and Removal and Dose Estimation," USNRC, Apr. 1998 4. Entergy Letter, PU2-E-03-20, "Entergy Nuclear Northeast 
-Indian Point2 -Power Uprating Program -Inputs Approved by the Technical Review Committee," 4/15/03 5. CN-REA-03-4, "Core Radiation Sources to Support the Indian Point 2 Power Uprate Project," Rev. 0, 4/3/03 6. NUREG/CR-5950,"Iodine Evolution and PH Control," Dec. 1992 7. CN-CRA-11-25, "Indiah Point 3 LOCA Doses including Contribution from Back-Leakage to RWST," IP-CALc-11-00080, (9/23/2011) 
: 8. CN-CDME-00-10, "Boric Acid Trisodium Phosphate Titration Curves," Revision 0, May 23, 2000 (copy of Table 3 is attached in Ref. 7) 9. NEA-00023, "Unit 2 TSC Personnel Doses from RG 1.183/NUREG-1465 Design Basis Loss-OF-Coolant-Accident, 11 Rev. 0, (3/22/05) 
: 10. IP-CALC-11-00063, "IPEC Unit 2 SIS & RHR Selected Internal Piping Volumes," Revision 0, (9/7/11)
Calculation No. IP-CALC-11-00091, Rev. O Attachment A, Page 1 ATTACHMENT A COMPUTER INPUTS & OUTPUTS Included in the EC 32007 is RADTRAD input and output files pertinent to section 6 of this calculation.
The following computer runs were considered in these analyses:
RADTRAD 3.03 Run # 1 Calculate of mass of iodine in the RWST (20 gph) Input Output Inventory Conc-iodineip220.psf Conc-iodineip220.o0 conc-iodineip2.nif Release Conv. Fae. Loca-i.rft dcfs.inp Run # 2 Calculate of mass of iodine in the RWST (29 gph) Input Output Inventory Conc-iodineip229.psf conc-iodineip2.nif Release Conv. Fae. Loca-i.rft dcfs.inp Run# 3 Calculate of mass of NaOH in the RWST (20 gph}
Calculation No. IP-CALC-11-00091, Rev. 0 Attachment A, Page 2 Input Output Inventory Conc-naohip220.psf Conc-naohip220.o0 con-naohip2.nif Release Conv. Fae. Con-naohip2.rft dcfs.inp Run # 4 Calculate of mass of NaOH in the RWST (29 gph) Input Output Inventory Conc-naohip229.psf Conc-naohip229.o0 con-naohip2.nif Release Conv. Fae. Con-naohip2.rft dcfs.inp Run# 5 Calculate CR & offsite doses from RWST back-leakage (20 gph) Input Output Inventory Release Conv.Fac Ip2rwst20.psf ip2rwst20.o0 ip2-core.nif eccsr.rft dcfs.inp Run# 6 Calculate CR & offsite doses from RWST back-leakage (29 gph) Input Output Inventory Release Conv. Fae Ip2rwst29.psf ip2rwst29.o0 ip2-core.nif eccsr.rft dcfs.inp Run # 7 Calculation No. IP-CALC-11-00091, Rev. 0 Attachment A, Page 3 Calculate TSC doses from RWST back-leakage (20 gph) Input Output Inventory Release conv. Fae Ip2tscrwst20.psf ip2tscrwst20.o0 ip2-core.nif eccsr.rft cfs.inp Run # 8 Calculate TSC doses from RWST back-leakage (29 gph) Input Output Inventory Release Conv. Fae Ip2tscrwst29.psf ip2tscrwst29.o0 ip2-core.nif eccsr.rft cfs.inp Calculation No. IP-CALC-11-00091, Rev. 0 Attachment B, Page 1 ATTACHMENT B TSC Doses IP2 LOCA TSC TEDE Doses (rem) for 20 & 29 gph Flow Rate C a s e Back-Leakage To RWST Calculated Containment 
& ECCS leakage (Ref. 9) Total TEDE Limit 20 gph 0.0407 2.482 2.52 5.0 29 gph 0.0635 2.482 2.55 5.0 See RADTRAD output ip2tscrwst20.o0 and ip2tscrwst29.o0 Calculation No. IP-CALC-11-00091, Rev. 0 Attachment C, Page 1 ATTACHMENT C Supporting Documentation:
Design Inputs (Total 9 Pages)}}